ML20134H756
| ML20134H756 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 02/06/1997 |
| From: | Dante Johnson WISCONSIN ELECTRIC POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| PBL-97-0044, PBL-97-44, NUDOCS 9702110448 | |
| Download: ML20134H756 (337) | |
Text
i Wisconsin l Electnc l POWER COMPANY _
i Point Beoch Nuclear Plant (414) 755-2321 ;
6610 huclear Rd, Two hers, WI 54241 PBL 97-0044 ,
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l February 6,1997 i l
Document ControlDesk U. S. NUCLEAR REGULATORY COMMISSION Mail Statinn PI-137 Washington, DC 20555 !
Ladies / Gentlemen: ,
DOCKET 50-301 RESTART DOCUMENTATION POINT BEACH NUCLEAR PLANT. UNIT 2 Pursuant to discussiens conducted at a January 31,1997, NRC/ Wisconsin Electric senier management meeting, we are enclosing documentation for review by your staff to support restan issues as identified on the Unit 2 Startup Commitment List. The items are:
- 9: Review the inservice testing (IS'I) acceptance criteria for the remaining IST pumps (fuel oil transfer, cable spreading room and control room ventilation; charging, boric acid transfer, component cooling water, and spent fuel pool cooling pumps) to ensure that the IST acceptance criteria meets the
, design basis / accident analysis requirements. Make changes as a result of this review.
On January 22,1997, we forwarded the close-out documentation on this item to you. This letter prosides the results of the independent review of this close-out package.
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- 10: ReviewtheISTaccept . e criteria for all IST valves to ensure the IST acceptance criteria meets i the design basis / accident an.dpis requirements. Make any changes necessary to as result of this l review.
l On January 22,1997, we forwarded the close-out do;umentation on this item to you. This letter provides the results of the independent resiew of this close-out package.
- 11: Complete the following regarding installed instnimentation: (a) Identify the Unit 2 installed ,
instruments used in the IST program; (b) Resiew the p rformance of the identified instruments over '
the last 3 years; (c) Resiew the suitability of the instnna ntation for use in the IST program; (d)
Review all IST pump hydraulic data over the past year for adverse trends. Make changes as necessary as a result of these actions.
[/
On January 22,1997, we forwarded the closc-out documentation on this item to you. This letter provides the results of the independent resiew of this close-ont package. h
- 26: Review ORT-3 and DCS 31.11 to ensure Technical Specification 15.4.6.A.2 testing includes dynamic loading of the emergency diesel generator (EDG) with sequences loads.
We are enclosing the revised test, guidance document and results of the independent review.
9702110448 970206 PDR ADOCK 05000301 p PDR A mMfan ofMiwvam Enrar Gepeatim
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1 PBL 97-0044 r February 6,1997 i Page 2 l
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- 65: Reinstallation of Unit 2 containment hatch third door to allow monitoring of door status.
We are enclosing the completed work order and results of the independent review. l In addition to the above, we are enclosing the Unit 2 Stanup Commitment List status update of February 6,1997, and [
the Unit 2 Restart Commitment Summary dated February 5,1997. ;
)
Sincerely, Douglas F. Johnson ,
Manager- ;
Regulatory Services & Licensing FAF/ sam Enclosures =
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- cc: NRC Regional Administrator i
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POINT BEACH UNIT 2 RESTAP.T COMMITMENT INDEPENDENT REVIEW RESULTS l C-S--mt ID Number 9 l
l Commitment Description l
Review the In Service Testing (IST) acceptance criteria for the remammg IST pumps (CCW, Charging, Boric Acid l Transfer, CR Chill Water, CSR Chill Water, SFP Cooling, and FO Transfer pumps) to ensure that the IST acceptance criteria meets the design basis / accident analysis requirements. Make any changes necessary as a result of this review.
The work has already been completed for the SI, RHR, AFW, SW, and Containment Spray pumps (the original group), so they are not included in this commitment.
The scope of this review will be ensuring that the IST acceptance criteria meets the design basis / accident analysis requirements. Should this review identify either generic issues or significant discrepancies which could negatively impact reactor safety, the scope of the review will be expanded. Where discrepancies are identified, appropriate corrective and preventive actions will be taken commensurate with their safety significance.
Reviewer 1
Review Methodology Instrument uncertainty and operability determmations were performed for the IST pumps evaluated by Startup Commitment #9. A representative sample of these documents was reviewed (20%) with emphasis placed on major equipment. These included: l
. Calculation No. 96-0279, " Uncertainty Associated with Instrumentation Used in IT-21 and IT-22 for Charging Pumps"
. Calculation No. 96-0284, " Uncertainty Associated with Instrumentation Used in IT-12 and IT-13 for CCW Pumps"
. Operability Determinadons included in CR 96-416: " Charging Pumps, Component Cooling Pumps."
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POINT BEACH UNIT 2 RESTART COMMITMENT INDEPENDENT REVIEW RESULTS Commitment ID Number 9 Revww Results The above calculations and operability determinations were reviewed for consistency and technical appropriateness. ;
No deficiencies were noted. The documents reviewed were of high quality and are characterized by thorough i research and attention to detail. The Operability Determmations reviewed included significant discussion of the ,
design bases and clear conclusions that IST acceptance criteria is appropriate and being achieved according to plant i procedural records. ,
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CCW Operability Determmation states that test flow for IT-12 and IT-13 is 3600 gpm. IT-13 sets mean average flow at 3500 gpm. Operability determmation is still valid on this point, since IT-13 flow is greater than the required design basis flow 3457 gpm (this value includes instrument uncertainty). It is noted, however, that the recommendation of the Operability Determination is to set flow at greater than the design basis flow. IT-13 is therefore in compliance with this recommendation. IT-12 is currently being revised and should be similarly reviewed when issued. Ultimately, the procedure flow value should be revised to match the operability recommendations l (setting flow at greater than the design basis flow (with instmment uncenainty included)), instead of the current procedural flow setting of 3500 gpm.
Recommendations Address the above procedure flow setting in next revision ofIT-13. Research IT-12 for similar applicability. l Based on the Independent Review, there are no items involved with Commitment #9 which would impede Unit 2 startup.
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l POINT BEACH UNIT 2 RESTART COMMITMENT '
INDEPENDENT REVIEW RESULTS Commitment ID Number 10 Commitment Description !
t Review the in Senice Testmg acceptance criteria for all IST valves to ensure that the IST acceptance criteria meets the design basis / accident analysis requirements. Complete necessary operability evaluations, revise procedures, and i resolve Unit 2 equipment discrepancies.
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De scope of this review will be examming the associated documents for accuracy and compliance with requirements, ,
per the criteria in the above paragraph. Should this review identify either generic issues or significant discrepancies !
which could negatively impact reactor safety, the scope of the review will be expanded. Where discrepancies are .
identified, appropriate corrective and preventive actions will be taken commensurate with their safety significance. ;
This commitment is also Enforcement Conference Commitment Item # 40.
Reviewer I
Review Methodology Perform a review of Point Beach Memo PBM 97-0036 evaluation ofIST stroke time acceptance criteria for IST !
valves. Review a 10 percent sampling of the design and licensing bases / stroke time data presented in the evaluation.
Review conclusions of the evaluation. ,
i Review Results ne evaluations contained in Point Beach Memo PBM 97-0036 required a significant preparation effort to assemble and evaluate design basis and Inservice Testing information for all Unit 1/2 and common IST valves. While minor editorial revisions were noted in the table presenting the valve design basis and IST stroke time information, the table is technically sound. Thejustifications presented in Attachment 2 of PBM 97-0036 were reviewed and were determined to be techically appropriate. Interviews conducted with IST personnel demonstrate the knowledge and familiarity with IST required to maintain a good IST program.
Recommendations ne independent review concurs with the recommendation of Point Beach Memo PBM 97-0036 that although the l
scope of Startup Commitment #10 and NRC Commitment NRC 96EC Action #40 have been satisfied, further (Phase
- 3) evaluation should be completed in order to prevent future questions if a valve would fall outside ofits preliminary design time. It would be prudent and proactive to continue such an effort.
Based on the Independent Review, there are no items involved with Commitment #10 which would impede Unit 2 startup.
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. . < i POINT BEACH UNIT 2 RESTART COMMITMENT INDEPENDENT REVIEW RESULTS Commitment ID Number 11 Commitment Description Complete the following regarding installed instrumentation used in the IST program:
. Identify the Unit 2 installed instruments used in the IST program. ,
I e Review the performance of the identified instruments over the last 3 years.
e Review the suitability of the instrumentation for use in the IST program, e Review all IST pump hydraulic data over the past year for adverse trends.
As necessary, make changes as a result of these actions.
Should these reviews identify either generic issues or significant discrepancies which could negatively impact reactor safety, the scope of the reviews will be expanded. Where discrepancies are identified, appropriate corrective and
, preventive actions will be taken commensurate with their safety significance.
l l This commitment is also Enforcement Conference Commitment item # 43.
Reviewer l -
1 Review Methodology Perform a review ofIST Instrumentation Review Final Report. Review a sampling of report data and the l conclusions and recommendations of the report. Review the Action item Status Report for NRC Enforcement l Conference item #43 which documents the resolutions to the recommendations of the IST Instrumentrion Review Final Report.
Rgview Results The report data, evaluations, and conclusions required a significant preparation effort. 'Ihe Independent Review j conducted interviews, data searches, and document reviews. As a result of the Independent Review, it is concluded that the report and its recommendations are technically sound. The Independent Review also resiewed each of the plant actions which were taken to address the report's Cndings. The conclusion of this Independent Review is that no outstanding items exist for this task which would impede Unit 2 startup. ;
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l i POINT BEACli UNIT 2 RESTART COMMITMENT ,
INDEPENDENT REVIEW RESULTS l i
i Commitment ID Number 11 1 Recommendations l '
The mstrumentation review conducted for Restart Commitment item 11 is a useful tool in not only m venfying that current IST instrumentation is appropriate and possesses sufficient reliability in fulfilling its design function, but also 1 as a long term practice. The independent review recommends that a streamlined database be set up for such a purpose and be evaluated on a periodic basis.
Based on the Independent Review, there are no items involved with Commitment #1I which would impede Unit 2 startup.
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. s. , . j POINT BEACH UNIT 2 COMMITMENT INDEPENDENT REVIEW RESULTS Commitment ID Number 26 Commitment Description Revise ORT-3 and DCS 3.1.11 to ensure Technical Specification 15.4.6.A.2 testing includes dynamic loading of the EDG with sequenced loads.
Reviewer Review Methodolery Review Technical Specification 15.4.6.A.2 for specific description of the requirements of this !
Emergency Power System Periodic Test. l Review the current revision to Operations Refueling Test - 3 (ORT-3), " Safety Injection Actuation With Loss of Engineered Safeguards AC " to verify the requirements of TS 15.4.6.A.2 are I captured.
[
Review FSAR Section 8.2.3, " Emergency Power" #
Review " Safeguards Sequence l ogic" drawings to the extent necessary to verify Load Shedding l requirements. [
Review the content of ORT-3 procedure with the author to ensure an overall understanding for the conduct of this technically complex, very detailed and integrated Emergency Power System ;
Testing.
Review the Duty & Call Superintendent Handbook section 3.1.11 (DCS 3.1.11) and verify these I mstructions and conclusions support the requirements of Technical Specification 15.4.6.A.2.
Review Results The commitment description contains a term " dynamic loading" and in the context of Technical Specification 15.4.6.A.2, this term addresses the following conditions of the test:
- automatically start the diesel, initiated by an actual interruption of normal AC power .
- demonstrate the designed load sheddmg 1
- following load shed, restoration of power to vital equipment Page 1 of 2 l
POINT BEACH UNIT 2 COMMITMENT '
INDEPENDENT REVIEW RESULTS Commitment ID Number 26 a together with a simulated safety injection signal l
- following at least 5 minutes ofloaded diesel generator operation, automatic load ,
shedding and restoration of vitalload are tested by manually tripping the diesel i generator output breaker
- demonstrate the diesel will start and assume required load in accordance with the timing sequence listed in FSAR Section 8.2 Operations Refueling Test - 3 (ORT-3), Revision 28, dated January 25,1997 was reviewed in detail and was verified to contain each element of the above requirements.
The FSAR Section 8.2 and Westinghouse Drawing 883D195 Sheets 8 and 9 " Safeguards Sequence Logic" were reviewed, and the ORT-3 procedure was confirmed to sequence and load shed in accordance with these design documents.
'Ihe " pre-job briefing" for the actual performance of the revised ORT-3 procedure was conducted on Wednesday,1/29/97. This meeting was attended by this member of the Independent Review Team. During the meetmg, the author reviewed the procedure content and sequence as well as the coordination requirements with the team of engineers, technicians, operators and others assigned to help perform this integrated test of the emergency power system. Throughout the meeting, the author interacted with the other participants to clear up any and all questions and concerns with the test procedure. Several, relatively minor, procedure corrections or additions were noted with expectations that temporary changes could be generated to resolve these items.
DCS 3.1.1I was veri 6ed to have been revised by a " Temporary Change Review and Approval" to bring the existing instruction and guidance in conformance with the Technical Specification 15.4.6.A.2. A permanent change to this document will replace the temporary hand wTitten changes in due time. This is considered to be satisfactory completion of, and conformance to this specific commitment.
Recommendations There are no recommendations. This commitment to revise ORT-3 and DCS 3.1.11 has been completed in a very professional manner. Based on this independent review, there are no items associated with this Commitment # 26 which would impede Unit 2 startup.
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b original marked-up procedure with anached form PBF-0026e'and change sheets shall be used in performma b task.
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~ Group tracking shau make a copy of form PBF-0026e and change sheets and soute this copy to the procedure owner.
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b procedure owner shan deserunne if this temporary procedure change is required for the other unit. If a temporary change i the procedure owner shan initiate this temporary procedure change. - , .* -
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b originator shan make as many copies of the marked-up procedure (including forms PBF-0026e into each manual designated on form FBF-0026h for immediate change. h. originator will then insert a copy of the marked-up 5.
Group tracking shall make a copy of forms PEF-0026e, PBF-0026h. change shee s. and the marked-up procedure, and route thern to Staff
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Group tracking shall snake a copy of form PBF-0026 and change sheets and route this copy to the procedure owner,
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b following is a brief summary of Technical Speci6 cation and NP 1.2.3 requirements. This summary does g supersede either of the consututas the nununum acceptable review and approval. -
M AJOR PRCCEDURE
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NUCI. EAR POWER DEPAR'IMENT PROCEDURE REVIEW AND APPROVAL CONTINUATION _ SHEET FROCEDURE bCO 3. / // > &sirsu E " A (11M A"2) L s > '
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DESC, RIBE DESIRED TRAINING OR REQUIRED READING, INCLUDING RESPONSIBLE GROUP (if applicable):
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Initials M PBF M 6e R2 vision 2 09/29/95
POINT BEACH NUCLEAR PLANT DCS 3.1.11 DUTY & CALL SUPERINTENDENT NNSR
,' HANDBOOK Revision 1 November 16, 1993 EMERGENCY DIESEL GENERATOR ANNUAL AUTOMATIC START TEST
1.0 REFERENCES
1.1 Technical Specification 15.4.6.A.2 1.2 Audit Finding Report A-TS-89-02-004 pg, i .2 "SSM ^0- ^5, igul;;crj !=r 1h mN M 1 l 1.4 FSAR Tables 8.2.1 and 8.2.2; Page 8.2-15 l , g .1 < ohnnnen r,4,,,,m,mn vi.u_onas7 a2,,e# nt/11/on
2.0 BACKGROUND
TS 15.4.6.A.2 describes the annual automatic start test of the emergency diesel generator (EDG) initiated by a loss of normal AC power with a simultaneous SI signal. Reference 1.2 noted that this specification was unclear as to whether the safeguards loads are required to be energized during the test or if certain breaken could be in " test" as is curTently the case.
The recommended corrective action in the AFR provided two options: Either change the specification to clarify this test requirement; or change the test to actually energize these
.;afeguards loads.
During MSSM 90-05, the MSS determined that the specification, as written, is adequate and
] that no change is required. The MSS also detennined that the test (ORT 3) is conducted in a manner which meets the subject specification. However, the MSS also believes that a TS interpretation would alleviate any perceived ambiguity regarding this specification.
3.0 d a:,exh de O fL # g,f -
MSS POSITION m e ehsudP/46p.<,m~
.7' ,y. .p-T. P Ly
<as l The purpose of the test covered by TS 15.4.6. A.2 is to'vansy-thafthe ET)G control systems and vital safeguards equipment control systems will function automatically in the event of a l loss of all normal AC station service power simultaneous with a safety injection signal.
It ! Se ugg p ;,;9 ,h,,; tis og, ,,-,ce,y ,se, ,i; ,he "i) equip e-' m '"y s'2r 2nd 4 nin. nniy ,he, eh, hr..ic,rt rn, ,h;c .nn;nm,n, nn,,,,, ;n ,h, e.n c, .. ...mee ,ma ,, ,w.
- /*/4 cemt '; e, L= scre&c "9 'he 'cadin;; ;equence p cvided ca hgc S.2-15 cf the TSAR.
l E i in t i, c c:ica h be d vu.
3.1 The monthly test performed in accordance with TS 15.4.6.A.1 demonstrates that the l EDG is capable of providing adequate power for operation of this equipment Page 1 of 2
--. .- .- -. - _ . - . - . ._ _ - .-. - _ - - - - _~_- - .-
POINT BEACH NUCLEAR PLANT .
DCS 3.1.11 '
- DUTY & CALL SUPERINTENDENT NNSR
. HANDBOOK Revision 1 I November 16, 1993 !
EMERGENCY DIESEL GENERATOR ANNUAL AUTOMATIC START TEST M Se pe=p: =d re!&:: f=: r~;ui-d :c ep ::: en = SI sig=!, per FSAR O 8.2@ -- 6-^ :'r'-d ic S ^penb!: by ::::: ccaic::d in accorhcc wnh T_ _C 1. .C . 3. _C _ .s TT. A. 1 /_ca r._n.,r
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7 - .1 C . 3 . .C ._TT. A. 1 /V_ I.I_D.nn. 7 _ n..n,\ , 1C A 0 1 O <
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s -
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,;n. .ma,e n_n_ _- i -_ n_ nai ;n_ 3. __
l f 3.3 Tb: ":i for di: :pci"^^ 02, fcund c: " g; 15.4.5 3,.;;;;;; de: ic test 3 damnnante 'w' the CE-r -1 " pr fit p~ :: fer :p;.=ien of eq ip.nca; (ca.cd
( h'it by TS 15. A.6..^. !) -" _' r= 'Er !S "3 yer ===1; =d S: :c:=! ;y;;;n;;
fer t' e reg" -& q"!p-en' -i" ^="'ia- ="tcru=*icany La the event of 2 'est of e'!
e.- ' ^.C ~rtic .:. /i= p^rc;r (===d by TS 15.4.5. A 2) l' s;n _._. , a__ -e ns 7___w;ii m_, n_r. rr
- v:, - -- en- nr --.;a. ---e.,rn ,.:.., sn m .. :, u - ~. -,- .-a n. , o u - ~. . u . .
r---- -----~'-/
- cre n.n,nin a we Te is a A A i e na eu an.co,. w;i;~, n_ r ,6 e_o_r.
_,, a__. :----- s:_-
.. _. ,a w., , , .
,,f. 9g, _&._..~. ... _ _ , . . u_ ..... - ..:no.a ,__ i;,, o n co r,m ,, ra c in a. ,,o,n ;,,.a ; , si c ,,c, n ,a
-^ rren!!y s'2n 2-d ran v !cng it 'he '"'^~i caatm' ry">=r --- ' de e-"n'ad to
_ functinn sn,nmntienliv r i
- *y %, !
l g'd. p-nra;not,e, ~ ;, is ,u ugg nne;,;nn ,u,7j[e~ loads listed on FSAR Tables 8.2.1 knd 8.2.2 .u ^
~
\
n=d "et rr !!y ::ar; during the portion of ORT 3 which fulfills this specification, en!) c,th2m l , M" the breakers for this equipment operatfTthe conect sequenceand at the correct time in accordance with the loading seque ce provided
- 8.24E of the FSAR.bt.a FA- ,,[
l MyMW M W hw ,, M
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i p m.m -fW .aa.ed bsAW 4 & ~*, n 2*" f~
I a ssu- ry.a 61 nj yd : 5 / abs wl'$ bN
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E. lIps ?L l
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I Page 2 of 2
^
NUCLEAR POWER BUSINESS UNIT ORT 3 OPERATIONS REFUELING TESTS MAlOR IPTE SAFETY INJECTION ACTUATION WITH LOSS OF Revision 28 ENGINEERED SAFEGUARDS AC '
" _* January 25,1997 UNIT 2 TOTAL REWRITE Date RECORD 93g PROCEDURE VERITIED CURRENT AND CHECKED FOR TEMPORARY CHANGES. IF FIELD COPIES REQUIRED. USE PBF.0026i1AW NP l.2 4 AND DOE COMPLETE Tills BLOCK.
Operations higr BY: DATE:
1.0 PURPOSE The purpose of ORT 3 iis to demonstrate proper:
1.1 Operation of saiety injection sequencing and diesel loading under conditions ofloss of engineered safeguards AC plus safety injection (Technical Specification 15.4.5-I.A &
15.4.6-A.2).
1.2 Automatic initiation of Control Room emergency filtration. (Technical Specification 15.4.11.2) 1.3 Operation of containment service water return bypass valves. (Technical Specification 15.4.5-I.C.1) 1.4 Containment isolation. (Technical Specification Table 15.4.1-2(13)).
t 1.5 Feedwater isolation. (Technical Specification Table 15.4.1-1(17)).
1.6 Operation of diesel generator automatic load shedding and restoration of vital loads ;
following a manual trip of the diesel generator output breaker. (Technical Specification 15.4.6-A.2) 1.7 Operation of 480 V and 4160 V saf'eguards undervoltage relays. Operation of 4160 V safeguards degraded grid voltage relays.
1.8 Operation of service water system with safety injection and less than 4 out of 6 service water pumps (Technical Specification Table 15.4.1-2(15)).
1.9 Operation of manual safety injection. (Technical Specification Table 15.3.5-3(1.a)).
1.10 Operation of AC to DC emergency lighting changeover. (Technical Specification 15.4.6.A.3)
Page1 of145 CONTINUOUS USE O .
NUCLEAR POWER BUSINESS UNIT ORT 3 OPERATIONS REFUELING TESTS MAJOR IPTE l SAFETY INJECTION ACTUATION WITH LOSS OF Revision 28 l% ENGINEERED SAFEGUARDS AC UNIT 2 January 25,1997 !
TOTAL REWRITE i l 2.0 DISCUSSION l 2.1 ORT 3 meets the Technical Specificaticn requirements for refueling frequency based ,
testing of safeguards systems and components. Testing is performed on a safeguards train related basis with one train tested at a time to verify train separation and train redundancy.
2.2 Undervoltage testing of 480 volt and 4.16 KV safeguards buses is performed in each safeguards power train. Loss of voltage, degraded grid voltage shon time delay, and degraded grid voltage long time delay schemes are tested independently. Additionally, each redundant train of slave or follower relays within each of the undervol' age protection schemes is functionally tested independent of the other for Train A or Train B of safeguards power supply on an alternating refueling shutdown interval. Train B is tested during U2R22.
2.3 ORT 3 maximizes the emergency diesel generator loading during the load sequencing test to the extent practical without affecting the safe power operation of Unit 1. Each Unit 2 safeguards power train normal and attemrte EDG is independently sequence loaded to the same degree from their respective Unit 2 safeguards power buses.
2.4 ORT 3 is performed with the core defueled and with the refueling cavity available to receive the low head and high head safety injection flow. For this test, the low head and high head SI systems are configured for power operation thus providing a realistic design load on the EDG with minimum core backpressure. The associated containment spray pump is operated on the high flow test line at design flow and is manually started at the same time as service water pump P-32F auto-sequences in the A train and P-32E auto-sequences in the B train. The containment vent cooler accident fans are auto-sequenced with no other normal or accident fans operating. For the B train only, P-38B auxiliary feedwater pump is auto-sequenced in the recire mode of operation.
These loads are maintained on each EDG for a minimum of five minutes after the last load has auto-sequenced as required by Technical Specification 15.4.6.A.2.
Subsequently, the automatic load shedding and restoration of aforementioned vital loads is tested again by manually opening the EDG output breaker as required by Technical Specification 15.4.6.A.2.
2.5 When an emergency diesel generator is aligned to a bus for testing, that generator is prevented from automatically closing to the opposite unit by placing the breaker control switch in the " PULLOUT" position. This alignment is performed to prevent possible l overloading of the generator being tested should an accident occur in Unit I during the test. Applicable LCOs are entered for this alignment, and the generator remains available to the unit through manual action per the test director and test coordinator.
Page 2 of145 CONTINUOUS USE
NUCLEAR POWER BUSINESS UNIT ORT 3 OPERATIONS REFUELING TESTS MAJOR IPTE SAFETY INJECTION ACTUATION WITH LOSS OF Revision 28
[q ENGINEERED SAFEGUARDS AC January 25,1997 UNIT 2 TOTAL REWRITE 2.6 ORT 3 testing has the potential for repeatedly cycling large motors (ie., service water pumps, safety injection pumps, auxiliary feedwater pumps, etc.) which have published motor starting duty limits. The most restrictive motor starting duty is as follows:
2 consecutive starts are permitted when the motor is cold.
I consecutive start is permitted when the motor is at operating temperature.
Subsequent motor starts are permitted if the motor is allowed to run 15 minutes for motor cooling or if the motor is secured for 60 minutes between short duration runs.
A motor is considered cold ifit has not operated for two hours.
3.0 PRECAUTIONS AND LIMITATIONS 3.1 11 4B boric acid transfer pump is the preferred pump for Unit I as its Unit I power supply is not interrupted during the test.
3.2 2A05 breakers are not seismically secured v hen placed in the TEST position. If a 2A05 breaker in the TEST position will be unattended for >2 hours, then the breaker must be racked out and seismically secured per OI 35, Section 5.5 or be racked in. 2A05 breakers that are in the TEST position as a requirement for ORT 3 shall be attended while in that position.
3.3 To preclude an overload possibility on a Unit I aligned EDG should Unit I experience an accident condition coincident with a loss of offsite power during the performance of ORT 3, the following provisions shall be maintained throughout this test:
During the load testing of G02 or G04 to their normal Unit 2 safeguards buses, G01 and G03 shall be aligned solely to their respective Unit I safeguards bus and with their respective output breaker to Unit 2 hey locked in the PULLOUT position. For the load testing of G01 or G03 as an alternate liI'G to Unit 2 safeguards buses, the G01/G03 normal output breaker to the respective Unit I bus shall first be placed in PULLOUT before enabling the G01/G03 alternate output breaker to Unit 2. The normal output breaker shall be maintained in PULLOUT for the duration of the G01/G03 load test and until the G01/G03 alternate output breaker is once again returned to the PULLOUT position at the end of the G01/G03 test. A 7-day LCO for Unit 1 emergency power unavailability shall be entered for the G01 and the G03 load test. Only one of the four EDGs shall be load tested to Unit 2 buses at a time.
3.4 IF, during the performance of this ORT, any shared safeguards system or component fails to perform its intended function, further testing shall be immediately suspended and the DCS notified. The impact of the failure on the operating unit shall be analyzed before resuming this test. )
Page 3 of 145 CONTINUOUS USE e
l NUCLEAR POWER BUSINESS UNIT ORT 3 OPERATIONS REFUELING TESTS MAJOR 3 IPTE l SAFETY INJECTION ACTUATION WITH LOSS OF Revision 28 l g. ENGINEERED SAFEGUARDS AC January 25,1997 UNIT 2 TOTAL REWRITE INITIALS 4.0 INITIAL CONDITIONS 4.1 Unit 2 is defueled.
t 4.2 Unit 2 reactor vessel and refueling cavity water levels are at the reactor vessel flange level to 6 inches above flange level. This corresponds to approximately 90-95% on the 2LI-447 vessel water level indicators.
4.3 All shared safeguards systems and components are operable except G04.
4.4 LHSI, HHSI, and containment spray systems and components are filled and vented and tested in accordance with their respective inservice test procedures.
l 4.5 Unit 1 is not in a limiting condition of operation.
4.6 Unit I and 2 safeguards buses are in a normal configuration and powered from offsite AC. G03 is aligned for standby emergency power to 1 A06 :
and 2A06. !
4.7 All safeguard systems-related work or testing on either or both units is suspended for the duration of this test.
4.8 Any non-safeguard systems-related work or testing on either or both units is evaluated as safe or is suspended for the duration of this test. Safe work is def'med as work or testing that does not challenge the integrity of the AC or DC distribution systems or the operability ofprocess systems or components in operation.
4.9 The following equipment is operating to prevent loss of process: ;
K-1B, WG compressor, if required.
l K-2A, IA compressor.
)
K-3A, SA compressor. I IP-4B, boric acid transfer pump, in " AUTO."
{
Plant radio standby power selected from B-43.
P-12B, spent fuel pool circulating pump.
j W-21 A and W-30A, PAB exhaust fans.
P-23A, RMUW pump in " AUTO" and aligned for blender services.
- W-107A and HX-191 A, computer room ventilation and A/C. -
IW-45A, bus duct cooling fan.
Page 4 of145 CONTINUOUS USE
l NUCLEAR POWER BUSINESS UNIT ORT 3 ;
OPERATIONS REFUELING TESTS MAJOR I IPTE }
SAFETY INJECTION ACTUATION WITH LOSS OF Revision 28
/ K'# )
ENGINEERED SAFEGUARDS AC January 25,1997 ,
UNIT 2 TOTAL REWRITE INITIALS ;
4.10 Components required operable for the test:
4.10.1 Valves i
2SI-841 A (Bkr only) 2SI-841B (Bkr only) 2SI-852A 2SI-852B 2SI-878B 2SI-878D SW-2816 SW-2817 2SW-2880 2SW-2907 2SW-2908 SW-2930A SW-2930B SW-LW61 !
SW-LW62 i
2CC-LW63 2CC-LW64 VNCR-4849C VNCR-4850 2MS-2017A, B, C, & D solenoids 2MS-2018A, B, C, & D solenoids AF-4020 AF-4022 2CS-466 2CS-476 2CS-480 l 2CS-481 SA-1 l SA-10 !
All CIVs of Attachment C Page 5 of145 CONTINUOUS USE l.
NUCLEAR POWER BUSINESS UNIT ORT 3 OPERATIONS REFUELING TESTS MAJOR IPTE SAFETY INJECTION ACTUATION WITH LOSS OF Revision 28 ;
p ,, ENGINEERED SAFEGUARDS AC January 25,1997 UNIT 2 TOTAL REWRITE INITIALS 4.10.2 Breakers All 2B03 bkrs All 2B04 bkrs All 2A05 bkrs !
All 2A06 bkrs 2A52-23 (2P-28A in TEST) 2A52-30 (2P-28B in TEST)
All battery charger supply contractors (8) 2-52/RTA (Reactor Trip Bkr) 2-52/RTB (Reactor Trip Bkr) 2B52 328H (W-13B1) 2B52-4211M (W-14B) 2B52-4212M (K-2B)
Spare DB-50 bkr 4.10.3 Components G01, G02, G03, G04 !
2P-10A & B !
2P-11 A & B 2P-14A & B l 2P-15A & B l P-32A, B, C, D, E & F P-38A & B 2W-1 Al, IBI, ICl, IDI W-85 and 86 D-07,09, D108 & 109 Multipoint recorder for CSR test points RMP 172 test equipment for G01 & G02 (if required)
Multipoint recorder for G03 ready to load relay at C81 4.11 An equipment / component tagout for this test is prepared in accordance with the listing of Attachment H.
4.12 Permission to Prepare for the Test The conditions required by this test are consistent with required plant conditions including equipment operability. Permission is granted to prepare for the test per test Section 5.0. -
DSS TIME DATE Page 6 of145 CONTINUOUS USE
NUCLEAR POWER BUSINESS UNIT ORT 3 ;
OPERATIONS REFUELING TESTS MAJOR IPTE ,
SAFETY INJECTION ACTUATION WITH LOSS OF Revision 28
- j. r ENGINEERED SAFEGUARDS AC January 25,1997 UNIT 2 TOTAL REWRITE INITIALS 5.0 PREPARATION FOR THE TEST NOTE: Steps 5.1 through 5.16 ofthis section may be performed out of the i sequence listed unless noted otherwise.
5.1 Perform emergency DC lighting system test per ORT 3, Attachment A. ,
l 5.2 Perform the following lineups:
5.2.1 Safeguards system valves and breakers per ORT 3, Attachment B.
5.2.2 Containment isolation valves per ORT 3, Attachment C.
5.3 Shutdown the following equipment:
Unit I and 2 boric acid evaporators.
Blowdown evaporator (steam out)
Letdown gas strippers per IT-605, Section 4.0 B-21 equipment, as required.
B-33 equipment, as required.
2B-31 equipment, as required.
5.4 The following steps are to be performed by the MTN group electricians with Operations group assistance / direction as required:
5.4.1 Install a spare DB-50 breaker in cubicle 2B52-35C of 2B03. 1 Leave breaker in a " TEST" condition.
MTN 5.4.2 2SI-841 A&B, accumulator discharge MOVs:
NOTE: In a cold or refueling shutdown,2SI-841A&B are procedurally shut and danger tagged. The MO V breakers are danger tagged and locked open.
- a. Verify 2SI-841 A&B breakers open:
~
i
! NUCLEAR POWER BUSINESS UNIT ORT 3 OPERATIONS REFUELING TESTS MAJOR IPTE 1 l
SAFETY INJECTION ACTUATION WITH LOSS OF Revision 28 g .3 .
~
ENGINEERED SAFEGUARDS AC January 25,1997 UNIT 2 TOTAL REWRITE -i INITIALS l
- b. Remove danger tag and remove lock on breakers:
- 1. 2852-324F l OPS
- CAUTION
- THE RECOVERY SECTION l (STEP 7.4.2) ASSUMES THAT THE I LOAD SIDE TERMINALS OF THE CONTACTOR AND THE MOTOR LEADS ARE CONNECTED TI-TI, T2-T2, AND T3-T3. IF THIS IS NOT THE CASE, STOP AND NOTIFY THE SUPERVISOR THAT A RECOVERY SECTION PROCEDURE CHANGE IS REQUIRED.
- 1. Identify cubicle 2B52-324F Check l
Concur l
- 2. Lift and tape the leads at h ammon loadside terminals of the contactors labeled T1, T2, and T3.
MTN
- 3. Identify cubicle 2B52-424F Check I Concur
- 4. Lift and tape the leads at the common loadside terminals of the contactors labeled T1, T2, and T3.
MTN
- 5. Verify the leads at the contactors of 2B52-324F and 2B52-424F are lifted. Verify 1
1 Page 8 of 145 CONTINUOUS USE
NUCLEAR POWER BUSINESS UNIT ORT 3 l OPERATIONS REFUELING TESTS MAJOR l IPTE
! SAFETY INJECTION ACTUATION WITH LOSS OF Revision 28 l gy, ENGINEERED SAFEGUARDS AC January 25,1997 UNIT 2 TOTAL REWRITE i INITIALS .
l d. Reclose breaker:
- 1. 2B52-324F e MTN '
- 2. 2B52-424F MTN 5.4.3 Defeat the main feed pump breaker interlocks:
- a. 2P-28A, main feed pump
- 1. In 2C03 at riser 50, identify terminals TPAB-11 and TPAD-11. Check t Concur
- 2. Jumper TPAB-11 to TPAD-11 (suction pressure, discharge valve, seal differential pressure)
MTN
- 3. In 2CO3 at riser 50, identify terminals TPAD-1 and ,
TPAD-2. Check l
Concur
- 4. Jumper TPAD-1 to TPAD-2 (oil pressure)
MTN
- 5. Identify slider TPAD-9 Check ;
I Concur
- 6. Open slider TPAD-9 (suction pressure)
MTN
- b. 2P-28B, main feed pump
- 1. In 2C03 at riser 50, identify terminals TPAJ-2 and ,
TPAL-1. Check Concur
- 2. Jumper TPAJ-2 to TPAL-1 (suction pressure, .
discharge valve, seal differential pressure)
MTN Page 9 of145 CONTINUOUS USE
NUCLEAR POWER BUSINESS UNIT ORT 3 OPERATIONS REFUELING TESTS MAJOR IPTE SAFETY INJECTION ACTUATION WITH LOSS OF Revision 28
- c. ENGINEERED SAFEGUARDS AC January 25,1997 UNIT 2 TOTAL REWRITE INITIALS
- 3. In 2CO3 at riser 50, identify terminals TPAK-3 and TPAK-4. Check Concur
- 4. Jumper TPAK-3 to TPAK-4 (oil pressure)
MTN
- 5. Identify slider TPAK-11 Check Concur
- 6. Open slider TPAK-11 (suction pressure) l MTN l
- CAUTION
- THE CONTROL SWITCH MUST BE IN
" PULLOUT" FOR ALL BREAKER REPOSITIONING IE., TEST, RACK-IN, RACK-OUT.
5.4.4 Place the main feed pump breakers in the TEST position with control power ON:
2A52-23,2P-28A MTN 2A52-30,2P-28B MTN 5.4.5 Prepare the DC buses for testing, as follows:
- a. Using OI 33, power D-02 from D-09 via IB-49.
- b. Using 0133, power D-03 from D-109 via 1B-32.
~
\
Page 10 of145 CONTINUOUS USE 9
l NUCLEAR POWER BUSINESS UNIT ORT 3 OPERATIONS REFUELING TESTS MAJOR IPTE I SAFETY INJECTION ACTUATION WITH LOSS OF Revision 28 l ,, y , ENGINEERED SAFEGUARDS AC January 25,1997 UNIT 2 TOTAL REWRITE l INITIALS l
NOTE: To maximi:e availability ofall battery chargers and chargerpower supplies, Steps 5.4.5.c through I 5.4.5.h should be performed <4 hours prior to test time.
- c. Danger tag open:
1
- 2. D-107 AC supply breaker on D-107 door panel.
- 4. 2B52-4212B, D-109 B Train AC supply.
OPS l
- f. Perform a phase-to-phase zero voltage check of contactors: l
MTN
- 2. 2B42-4212B on the MCC 2B-42 side of the contactor. l MTN l
Page 11 of145 CONTINUOUS USE
NUCLEAR POWER BUSINESS UNIT ORT 3 OPERATIONS REFUELING TESTS MAJOR i IPTE SAFETY INJECTION ACTUATION WITH LOSS OF Revision 28
/E@ ENGINEERED SAFEGUARDS AC January 25,1997 UNIT 2 TOTAL REWRITE INITIALS
- g. Defeat the D-09 and D-109 contactor interlocks by opening ;
the following sliders in 2C-20. ASIP:
- 1. Identify TBl1-8 IB52-491 interlock Check ,
- l Concur l
- 2. Open TB11-8 IB52-491 interlock.
MTN ;
- 3. Identify TB27-4 2B52-391 interlock. Check '
4
)
Concur
- 4. Open TB27-4 2B52-391 interlock.
MTN l
- 5. Identify TB29-1 1B52-3212H interlock. Check ,
Concur j
- 6. Open TB29-1 1B52-3212H interlock.
i MTN i
- 7. Identify TB9-112B52-4212B intericek. Check i Concur
- 8. Open TB9-112B52-4212B interlock.
MIN i NOTE: The 2C-20, ASIP operator and a MTN electrician, i at the contactorpanel, must communicate to l accomplish thefollowingstep. \
- h. Close the following contactors by holding the associated control switch on 2C-20 in "CLOSE" while the electrician manually closes the contactor to backfeed the contactor control relay.
- 2. 2B42-4212B '
OPS 5.4.6 Perform RMP 172, " Monitor Emergency Diesel Generator Fast l Start Voltage and Breaker Closure," through Section 7.3, Test Equipment Connections for G01 and G02, if required. .
MTN Page 12 of145 CONTINUOUS USE
1 NUCLEAR POWER BUSINESS UNIT ORT 3 OPERATIONS REFUELING TESTS - MAJOR IPTE SAFETY INJECTION ACTUATION WITH LOSS OF Revision 28 g.; ENGINEERED SAFEGUARDS AC January 25,1997 UNIT 2 TOTAL REWRITE INITIALS 5.5 The followine steps are to be nerformed by the I&C croup. :
NOTE: Ifdummy test signals poweredfrom the lighting system are insertedprior to the test ofDClighting specified in Step S.1, h an unscheduled RPS trip signal will be generated.
5.5.1 Pretest portion ofICP 10.22A completed to clear all RPS trip .
signals. Do not restore safeguards test switches to normal at thi s time.
I&C 5.5.2 Verify that an auto Si signal from pressurizer low pressure is available so that by unblocking SI, auto SI actuation will occur.
'I&C 5.5.3 Unit 14160 volt bus fast transfer control circuit continuity i check for bus tie breakers I A52-37 and 1 A52-55. !
l
- a. In safeguards panel 2C-157, measure ~ -67 Vdc to ground at TB6C-9.
Record voltage. Vdc I I&C
- b. In safeguards panel 2C-157, measure ~ -67 Vdc to ground l at TB6D-1.
Record voltage. Vdc l I&C l Page 13 of145 CONTINUOUS USE
l NUCLEAR POWER BUSINESS UNIT ORT 3 l
! OPERATIONS REFUELING TESTS MAJOR ;
IPTE SAFETY INJECTION ACTUATION WITH LOSS OF Revision 28
'c, . ENGINEERED SAFEGUARDS AC January 25,1997 UNIT 2 TOTAL REWRITE INITIALS 5.5.4 Multipoint recorders connected to monitor timed sequence action of the following:
IC Initials 2P-15A, SI pump breaker 2P-15B, SI pump breaker l 2P-10A, RHR pump breaker 2P-10B, RHR pump breaker l P-38A, AF pump breaker l P-38B, AF pump breaker i P-32A, SW pump breaker )
P-323, SW pump breaker P-32C, SW pump breaker l
P-32D, SW pump breaker l P-32E, SW pump breaker P-32F, SW pump breaker 2W-1 Al, VNCC fan breaker 2W-1B1, VNCC fan breaker 2W-1C1, VNCC fan breaker 2W-IDI, VNCC fan breaker G01 or G02 to 2A05 breaker 4 G03 or G04 to 2A06 breaker 2A05, voltage sensor 2A06, voltage sensor I 2C-157, A SI signal 2C-167, B SI signal 5.6 Align the MSIV circuits for testing as follows:
5.6.1 Verify operating air is isolated to:
2MS-2017 2MS-2018 Page 14 of 145 CONTINUOUS USE
l NUCLEAR POWER BUSINESS UNIT ORT 3 OPERATIONS REFUELING TESTS MAJOR IPTE l SAFETY INJECTION ACTUATION WITH LOSS OF Revision 28 l % ENGINEERED SAFEGUARDS AC January 25,1997 UNIT 2 TOTAL REWRITE INITIALS 1
5.6.2 Verify DC power breaker closed 1 l D-1901 MSIV solenoids, Train B D-2201 MSIV solenoids, Train A 5.6.3 Place the control switch to the "OPEN" position for:
I 2MS-2017 MSIV solenoids, Train B 2MS-2018 MSIV solenoids, Train A 5.6.4 Verify that a containment high pressure signal does not exist.
5.6.5 Locally, at the MSIV racks, reset by latching the four trip solenoids for each MSIV.
1 2MS-2017 A, B, C, & D l
2MS-2018A, B, C, & D l
5.6.6 Verify that a 1 out of 2 high steam flow isolation signal is present for each steam generator by observing the bistable trip status panel.
l 5.6.7 Verify that a 2 out of 4 low Tava isolation signal is present by observing the bistable trip status panel.
l l
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l Page 15 of145 CONTINUOUS USE
NUCLEAR POWER BUSINESS UNIT ORT 3 OPERATIONS REFUELING TESTS MAJOR IPTE SAFETY INJECTION ACTUATION WITH LOSS OF Revision 28 l '
pg ENGINEERED SAFEGUARDS AC January 25,1997 UNIT 2 TOTAL REWRITE INITIALS
- CAUTION
- THE CONTROL SWITCH MUST BE IN " PULLOUT" FOR ALL BREAKER REPOSITIONING IE., TEST, RACK-IN, RACK-OUT. -
5.7 Verify the breaker racked in and control power QN for the following:
NOTE: Reactor trip breakers must be rackedin versus testposition ,
for the mainfeed valves to open.
2-52/RTA Reactor trip bkr.
2-52/RTB Reactor trip bkr 1B52-10C P-32A SW pump 1B52-11C P-32B SW pump IB52-12C P-38A AF pump 1B52-20C P-32C SW pump
- 2B52-26A 2W-1C1 VNCC Fan 2B52-26B 2W-1D1 VNCC Fan '
2B52-27B P-32D SW pump 2B52-27C P-32E SW pump i 2B52-29A 2P-10B RHR pump 2B52-31C P-38B AF pump 2B52-34B P-32F SW pump 2B52-36A 2P-10A RHR pump ,
2B52-39A 2W-1 Al VNCC Fan 2B52-39B 2W-1B1 VNCC Fan l
2A52-67 G02 to 2A05 l 2A52-93 004 to 2A06
- CAUTION
- THE CONTROL SWITCH MUST BE IN " PULLOUT" FOR ALL BREAKER REPOSITIONING IE., TEST, RACK-IN, RACK-OUT.
5.8 Place the following equipment breakers in the " TEST" position:
2B52-28A 2P-2C Charging pump 2B52-29B 2T-1D Przr heater 2B52-30C 2T-1E Przr heater 2B52-33C Multi-Amp Test stand
, 2B52-36B 2T-1C Przr heater i 2B52 37A 2P-2A Charging pump ,
l 2B52-37B 2P-2B Charging pump i
Page 16 of145 CONTINUOUS USE
! i l NUCLEAR POWER BUSINESS UNIT ORT 3 l OPERATIONS REFUELING TESTS MAJOR iPTE l , SAFETY INJECTION ACTUATION WITH LOSS OF Revision 28 i
' thn ENGINEERED SAFEGUARDS AC January 25,1997 UNIT 2 l
TOTAL REWRITE l INITIALS I 1
l 5.9 Align Unit 2 RCDT as follows: 1 1
5.9.1 Verify shut 2SF-816 and 2RH-715D. l 5.9.2 Place the RCDT pump control switches in " PULLOUT".
2P-18 l 2P-66 5.9.3 Danger tag shut IA supply to 1 WL-1698, then fail instrument air to 1WL-1698, the Unit i RCDT drain to -19' sump CIV.
l 5.9.4 Danger tag shut the following valves:
WL-1698A, Unit I and Unit 2 RCDT drain isolation.
WL-1698B, drain line IVTC. l 2WL-1726,2P-18 discharge.
2WL-1727,2P-66 discharge.
5.9.5 Place the RCDT pump suction valve control switches in
" AUTO":
2WL-1003A 2WL-1003B l
5.9.6 Fill the RCDT until 2WL-1003A&B automatically open.
5.9.7 Verify 2WL-1721 open with control switch in the " AUTO" position.
I 5.9.8 Danger tag and tape the control switch for 2WL-1698 in the "OPEN" position.
f l
l Page 17 of145 CONTINUOUS USE
NUCLEAR POWER BUSINESS UNIT ORT 3 i
OPERATIONS REFUELING TESTS MAJOR ,
IPTE I
. SAFETY INJECTION ACTUATION WITH LOSS OF Revision 28 !
g, ENGINEERED SAFEGUARDS AC January 25,1997 UNIT 2 TOTAL REWRITE INITIALS l 5.10 When the blowdown evaporator and letdown gas strippers are in a stable shutdown condition, then:
l t l 5.10.1 Danger tag shut 1MS-251, Unit 1 RS supply.
5.10.2 Danger tag shut 1MS-252, Unit 1 RS supply.
5.10.3 Open SA-10, Unit 2 RS trip valve.
5.10.4 Obtain a key from the DSS for key-operated 43/ sal switch on C-180 and place 43/ sal switch in the " BYPASS" position.
5.10.5 Open SA-1, RS PCV, with the controller in the " MANUAL" mode. Verify SA-1 open by local VPI.
5.10.6 When RS steam pressure is <10 psig, then danger tag open l RS-64, high point vent.
5.11 Alien Unit 2 AF system for the test.
5.11.1 Shut AF-32, P-38A discharge to 2HX-1 A SG.
5.11.2 Shut AF-45, P-38B discharge to 2HX-1B SG.
5.12 Main Feed Reculatine Valves and Bypasses 5.12.1 Verify that no T 3vo test signal is present in any of the four TAVG channels. All TAVG channels indicate <550'F.
5.12.2 Verify the following valves are not gagged mechanically, have IA aligned, and that the associated VPI is displaying a fully i shut valve:
2CS-466 Main feed regulator l 2CS-476 Main feed regulator ;
i 2CS-480 Main feed regulator bypass !
2CS-481 Main feed regulator bypass I i
. i Page 18 of145 CONTINUOUS USE
- .- ._ - . _ _ = - . .. . . - _
l NUCLEAR POWER BUSINESS UNIT ORT 3 j OPERATIONS REFUELING TESTS MAJOR ;
i IPTE
- l. SAFETY INJECTION ACTUATION WITH LOSS OF Revision 28 l /5 ENGINEERED SAFEGUARDS AC January 25,1997 UNIT 2 TOTAL REWRITE INITIALS 5.13- 2P-14A&B Snray Pumn Alienment:
NOTE: This section assumes that both trains of the Containment Spray System (exclusive ofthe Spray Additive Tank to ;
2SI-874A&B) are alignedper CL 7A.
l NOTE: A second operator is required in the PAB to assist in the pre-pressurization and draining of the spray header.
NOTE: 2P-14B is preppedfirstfollowed by 2P-14A in this section because 2P-14A is then left in a condition to be testedfirst in procedure Section 6.0.
l 5.13.1 Verify the oil level of 2P-14B at the propr level. Contact the DSS for the type of oil required.
h 5.13.2 Place the 2P-14B control switch to " PULLOUT."
5.13.3 Clean boric acid off of 2P-14B seal area.
5.13.4 Unlock and shut 2SI-874B, Train B eductor suction.
- CAUTION
- VERIFICATION OF NEXT STEP IS REQUIRED.
VALVE MUST BE SHUT TO PREVENT SPRAY OF CONTAINMENT.
5.13.5 Unlock and shut firmly 2SI-868B, containment spray header isolation (yellow handwheel). /
NOTE: The specified airpressure in Steps 5.13.6 and 5.13.10 s based on afull RWSTof 98%. Pressure should be reduced at a rate of1 psigfor every 3.5% level that RWSTlevelis <S8%.
5.13.6 Attach a SA line with pressure gauge to 2SI-869B, header air test connection, unlock 2SI-869B and pre-pressurize the header -
to 27 psig (or as determined from the level calculation).
5.13.7 Connect hoses for level gauge, LG-916, to 2SI-D31 and 2SI-V24 and place level gauge in service. ,
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,y ENGINEERED SAFEGUARDS AC January 25,1997 UNIT 2 TOTAL REWRITE INITIALS 5.13.8 Unlock and open:
- a. 2SI-862H,2P-14B high flow test line isolation.
5.13.9 Position 2SI-862J, high flow test line FCV, to 3 and 3/4 turns open (~700 gpm position).
NOTE: The objective of the next two steps is to monitorfor air leakage of the air cushion at 251-868B by correlation to a water level rise in a verticalsection ofpipe.
5.13.10 Increase air pressure as in Step 5.13.6 to a maximum of 29 psig until water level appears in the level gauge.
5.13.11 Shut 2SI-869B and disconnect the SA supply.
5.13.12 Observe level over a period of 5 minutes and verify level is holding, indicating 2SI-868B is leak tight. A level increase of s2.0 inches in 5 minutes is acceptable for a pump run time of one hour.
5.13.13 Shut 2SI-D31 and V24.
5.13.14 Open SI-917B, level gauge drain, to prevent overpressurizing gauge.
5.13.15 Verify shut 2SI-871 B, LHSI cross-connect MOV, then verify open 2SI-870B,2P-14B RWST suction MOV.
5.13.16 Open 2SI-860C,2P-14B discharge MOV.
5.13.17 Open 2SI-860D,2P-14B discharge MOV.
5.13.18 Open 2SI-848K and record the static suction pressure for 2P-14B. psig
. \
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l Page 20 of 145 CONTINUOUS USE i
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i NUCLEAR POWER BUSINESS UNIT ORT 3 OPERATIONS REFUELING TESTS MAJOR l IPTE !
l SAFETY INJECTION ACTUATION WITH LOSS OF Revision 28 ly# ENGINEERED sal EGUARDS AC- January 25,1997 UNIT 2 '
TOTAL REWRITE INITIALS
- CAUTION
- MONITOR AND VERIFY 2P-14B SUCTION '
PRESSURE 27.8 PSIG PER 2PI-933D ANYTIME ;
FLOW IS CHANGED.
l l 5.13.19 Verify 2P-14B breaker on 2B04 is racked in, then start 2P-14B. -i i
P j 5.13.20 Verify 2P-14B pump suction pressure 27.8 psig.
l 5.13.21 Vent the 2 FIT-661 sensing lines of all air.
- CAUTION
- DO NOT EXCEED 1600 GPM.
5 13.22 Position 2SI-8623 for a test line flow of 1200 gpm per 2FI-661. !
Record 2SI-862J throttled position for 1200 gpm in number of turns open to the nearest 1/8 turn. turns >
l 5.13.23 Check the pump and mechanical seals for excessive leakage,
! unusual noise, and overheating.
l 5.13.24 Shut 2SI-848K,2P-14B suction gauge isolation.
1 5.13.25 Stop 2P-14B by placing control switch to " PULLOUT".
5.13.26 Flush the seal area of 2P-14B by spraying the seal area with warm DI water.
5.13.27 Shut 2SI-860C&D.
5.13.28 Shut 2SI-862H,2P-14B high flow test line isolation.
5.13.29 Shut 2SI-862J, high flow test line FCV.
l 5.13.30 Shut SI-917B, level gauge drain.
NOTE: A second operator is required in the PAB to assist in the pre-pressurization and draining ofthe spray header.
5.13.31 Verify the oil level of 2P-14A at the proper level. Contact the i DSS for the type of oil required. .- :
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SAFETY INJECTION ACTUATION WITH LOSS OF Revision 28
} p .s ENGINEERED SAFEGUARDS AC January 25,1997 UNIT 2 TOTAL REWRITE INITIALS 5.13.32 Place the 2P-14A control switch to " PULLOUT." i l
5.13.33 Clean boric acid ofTof 2P-14A seal area. l 5.13.34 Unlock and shut 2SI-874A, Train A eductor suction.
- CAUTION
- VERIFICATION OF NEXT STEP IS REQUIRED. i VALVE MUST BE SHUT TO PREVENT SPRAY OF CONTAINMENT.
5.13.35 Unlock and shut firmly 2SI-868A, containment spray header isolation (green handwheel). /
NOTE: The specified airpressure in Steps 5.13.36 and 5.13.40 is based on afull R WST of 98%. Pressure should be reduced at i the rate ofI psigfor every 3.5% level that RWSTlevel is <98%.
5.13.36 Attach a SA line with pressure gauge to 2SI-869A, header air i test connection, unlock 2SI-869A and pre-pressurize the header to 27 psig (or as determined from the level calculation). ;
1 5.13.37 Connat hoses for level gauge, LG-916, to 2SI-D31 rnd j
2SI-V24 and place level gauge in service. i l
5.13.38 Unlock and open 2SI-862G,2P-14A high flow test line isolation.
5.13.39 Position 2SI-862J, high flow test line FCV, to 3 and 3/4 tums open (~700 gpm position).
NOTE: The objective ofthe next two steps is to monitorfor air leakage ofthe air cushion at 2-SI-868A by correlation to a water level rise in a vertical section ofpipe.
5.13.40 Increase air pressure as in Step 5.13.36 to a maximum of 29 psig until water level appears in the level gauge.
l J
5.13.41 Shut 2SI-869A and disconnect the SA supply. .
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' OPERATIONS REFUELING TESTS MAJOR IPTE l SAFETY INJECTION ACTUATION WITH LOSS OF Revision 29
,u, ENGINEERED SAFEGUARDS AC January 2f,1997 ;
UNIT 2 TOTAL R EWRITE ,
INITIALS 5.13.42 Observe level over a period of 5 minutes and verify level is holding, indicating 2SI-868A is leak tight. A level increase of s2.0 inches in 5 minutes is acceptable for a pump run time of one hour.
5.13.43 Shut 2SI-D31 and V24.
5.13.44 Open 2SI-917B, level gauge crain, to prevent overpressurizing gauge.
5.13.45 Verify shut 2SI-871 A, LHSI cross-connect MOV, then verify open 2SI-870A,2P-14A RWST suction MOV.
5.13.46 Open 2SI-860A,2P-14A discharge MOV.
5.13.47 Open 2SI-860B,2P-14A discharge MOV.
5.13.48 Open 2SI-848J and record the static suction pressure for l
2P-14A. psig
- CAUTION
5.13.49 Verify 2P-14A breaker on 2B03 is racked in, then start 2P-14A.
5.13.50 Verify 2P-14A pump suction pressure 27.8 psig.
5.13.51 Vent the 2 FIT-661 sensing lines of all air.
- CAUTION
- DO NOT EXCEED 1600 GPM.
5.13.52 Position 2SI-862J for a test line flow of 1200 gpm per 2FI-661.
l 5.13.53 Check the pump and mechanical seals for excessive leakage, i unusual noise, and overheating.
5.13.54 Shut 2SI-848J,2P-14A suction gauge isolation. -
! 4 h
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NUCLEAR POWER BUSINESS UNIT ORT 3 OPERATIONS REFUELING TESTS MAJOR IPTE SAFETY INJECTION ACTUATION WITH LOSS OF Revision 28 A& ENGINEERED SAFEGUARDS AC January 25,1997 !
UNIT 2 TOTAL REWRITE ,
INITIALS 5.13.55 Stop 2P-14A by placing control switch to " PULLOUT".
5.13.56 Flush the seal area of 2P-14A by spraying the seal area with warm DI water.
5.13.57 Shut 2SI-860A&B.
5.14 2P-15A&B HHSI Pumn Alienment NOTE: This section assumes that both trains ofHHSI are aligned per CL 7A and have beenfilled and testedper IT 02.
5.14.1 Position or verify the position of the folloiving train A main flow path HHSI valves:
2SI-878B,2P-15A to CL injection MOV Open 2SI-878D,2P-15A to CL injection MOV Shut 2SI-866A,2P-15A discharge isol. MOV Shut 2SI-896A,2P-15A suction isol. MOV Open 2SI-825A, RWST to SI pump suction MOV Open 5.14.2 Position or verify the position of the following train B main flow path HHSI valves:
2SI-866B,2P-15B discharge isol. MOV Shut 2SI-8968,2P-15B suction isol. MOV Open 2SI-825B, RWST to SI pump suction MOV Open 1
2SI-878A,2P-15B to core deluge isol. MOV Shut 2SI-878C,2P-15B to core deluge isol. MOV Shut 2SI-878E,2P-15B to CL injection manual Open l
2SI-878F,2P-15B to CL injection manual Open i 5.14.3 Position or verify the position of the following valves in the HHS1 pump mini-recire flow path:
l l 2SI-876A,2P-15A mini-recire isol Open l 2SI-876B,2P-15B mini-recirc isol Open
, 2SI-897A, Si test line iml. AOV Gagged Open l 2SI-897B, SI test line isal. AOV Gagged Open Page 24 of 145 CONTINUOUS USE
NUCLEAR POWER BUSINESS UNIT ORT 3 OPERATIONS REFUELING TESTS MAJOR IPTE <
SAFETY INJECTION ACTUATION WITH LOSS OF Revision 28 g' ,'_'
ENGINEERED SAFEGUARDS AC January 25,1997 UNIT 2 TOTAL REWRITE INITIALS +
5.14.4 Place the 2P-15A&B control switches to " PULLOUT", then rack-in the following breakers:
2A52-74,2P-15A breaker on 2A05 i 2A52-88,2P-15B breaker on 2A06 5.14.5 Start /stop 2P-15A&B to verify breaker operability, then return 2P-15A&B control switches to " PULLOUT". ,
l 5.15 2P-10A&B LHSI Pump Alienment l NOTE: This section assumes that both trains ofDii! ore alignedper CL 7B andhave been testedperIT04 orIT04A.
5.15.1 Stop 2P-10A&B if operating and place control switches to ,
" PULLOUT". l l
i 5.15.2 If operating, secure lower cavity purification by:
- a. Stopping P-33.
I t
2CV-427, normal letdown isolation MOV 2CV-371B, normal letdown manuas isolation 2RH-715C, RHR letdown manual isolation 1
5.15.4 Split the two RHR trains by shutting:
l 2RH-713A,2P-10A&B discharge cross-connect 2RH-716D, RHR HX outlet cross-connect !
l I
Page 25 of145 CONTINUOUS USE i . .
NUCLEAR POWER BUSINESS UNIT ORT 3 OPERATIONS REFUELING TESTS MAJOR IPTE SAFETY INJECTION ACTUATION WITH LOSS OF Revision 28 ENGINEERED SAFEGUARDS AC January 25,1997 UNIT 2 TOTAL REWRITE INITIALS ,
5.15.5 Align train A for LHSI by aligning the following valves:
Position 2RH-704A,2P-10A loop suction manual isol. Shut 2SI-851 A,2P-10A Sump B suction MOV Shut 2SI-852A,2P-10A core deluge isol. MOV Shut 2SI-720. RHR to loop discharge MOV Shut 2RH-624, RHR HX outlet HCV Open 2RH-626, RHR HX bypass HCV Shut 2RH-733A,2P-10A mini-recirc manual isol. Open 2SI-856A,2P-10A RWST suction MOV Open 5.15.6 Align train B for refueling cavity / reactor vessel pumpback to the RWST by aligning the following valves:
NOTE: This step aligns P-10Bforflow test per Step 5.15.7, then Step 5.15.9 completes cavity pumpback alignment.
Position 2RH-700, RHR loep suction isol. MOV Open 2SI-701, RHR loop suction isol. MOV Shut 2SI-851B,2P-10B Sump B suction MOV Shut 2SI-852B,2P-10B core deluge discharge MOV S' hut 2SI-856B,2P-10B RWST suction MOV Open ,
2PM
- 33B,2P-10B mini-recirc manualisol. Open 2Ad 706B,2P-10B high flow test line isol. Open 2RH .'42, RHR high f'ew test line isol. Open 2RH-7.'2B, RHR high flow test line FCV Shut 5.15.7 Start 2P-10B, then throttle ope: ;M-742B for a high flow test line flow rate of 1560-1600 gpm. Lock 2RH-742B handwheel in position.
5.15.8 Stop 2P-10B and place control switch to " PULLOUT".
l 5.15.9 Align 2P-10B suction to the loop by shutting 2SI-856B, then opening 2RH-701. :
Page 26 of145 CONTINUOUS USE 6
- NUCLEAR POWER BUSINESS UNIT ORT 3 OPERATIONS REFUELING TESTS MAJOR IPTE SAFETY INJECTION ACTUATION WITH LOSS OF Revision 28 ENGINEERED SAFEGUARDS AC January 25,1997 UNIT 2 TOTAL REWRITE INITIALS j 5.l f - Pre-Test Briefine NOTE
- The test director is normally an offshift SRO shift superintendent directly responsiblefor theperformance of \
this test. The test coordinator is an operation staffor site engineering person intimatelyfamiliar with the test to assist ,
the test director. i 5.16.1 The test director shall assign personnel for the test in !
accordance with the requirements of Attachment G.
5.16.2 An Operations Duty and Call person shall brief the test crew on I the expectations of management in accordance with NP 1.2.6.
l 5.16.3 The test coordinator and/or the test director shall brief the test performers / observers of their assigned responsibilities. They i should review the test with the participants to the degree I necessary to assure a successful test with particular attention to plant and personnel safety.
5.17 When <2 Hours to Test Time:
5.17.1 Verify Z-14, turbine building crane, is not in use, then danger !
tag open the power supply disconnect switch for the DSS. I 5.17.2 Verify IZ-30, U1 facade elevator, is not in use, then danger tag open breaker No.1 in PP9 for the DSS.
5.17.3 Verify Z-29, Unit I turbine building elevator, is not in use, then danger tag open breaker BS2-211DL for the DSS.
5.17.4 Position the " PREFERRED START" selector switch to start circuit 2 for:
G01 l
l G02 l
i Page 27 of145 CONTINUOUS USE l
NUCLEAR POWER BUSINESS UNIT ORT 3 OPERATIONS REFUELING TESTS MAJOR IPTE SAFETY INJECTION ACTUATION WITH LOSS OF Revision 28 g& ENGINEERED SAFEGUARDS AC January 25,1997 UNIT 2 TOTAL REWRITE INITIALS 5.17.5 Place each units' SG blowdown /AF pump interlock defeat switch to the "ON" position:
Unit 1 i 1
Unit 2 5.17.6 If Unit 1 SG blowdown is directly to the blowdown tank and the blowdown heat exchangers cannot be placed in service, then secure Unit 1 SG blowdown.
1 5.17.7 Close the main feed pump breakers for: 1 2P-28A 2P-28B 5.17.8 With the assistance of a maintenance electrician, perform the following for 2B52-40C,2B03/B04 bus tie:
- a. Verify 2B52-40C control switch in " PULLOUT".
- b. Install control power fuses for 2B52-40C. l l
- c. Place 2B52-40C to the " TEST" position.
I
- d. Place 2B52-40C control switch to " AUTO".
- e. Locally close 2B52-40C.
- f. Red flag the control switch for 2B52-40C and verify proper breaker indication.
proper breaker indication.
- h. Place 2B52-40C control switch to " PULLOUT".
- i. Remove 2B52-40C control power fuses. .
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ENGINEERED SAFEGUARDS AC January 25,1997 l UNIT 2 TOTAL PIWRITE INITIALS 5.17.9 With the assistance of a rnaintenance electrician, perform the following for 2B52-39C,2B01/B03 bus tie:
- a. Verify 2B52-39C control switch in " PULLOUT".
- b. Verify control power fuses installed for 2B52-39C.
- c. Place 2B52-39C to the " TEST" position.
- d. Place 2B52-39C control switch to " AUTO".
- e. Locally close 2B52-39C.
- f. Red flag the control switch for 2B52-39C and verify proper breakerindication.
- g. Open 2B52-39C with the C02 control switch and verify proper breakerindication.
- h. Place 2B52-39C control switch to " PULLOUT".
5.17.10 With the assistance of a maintenance electrician, perform the following for 2B52-26C,2002/2B04 bus tie:
- a. Verify 2B52-26C control switch in " PULLOUT".
- b. Verify control power fuses installed for.2B52-26C.
- c. Place 2B52-26C to the " TEST" position.
- d. Place 2B52-26C control switch to " AUTO".
- e. Locally close 2B52-26C.
- f. Red flagTthe control switch for 2B52-26C and verify proper breaker indication.
- h. Place 2B52-26C control switch to " PULLOUT".
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NUCLEAR POWER BUSINESS UNIT ORT 3 OPERATIONS REFUELING TESTS MAJOR IPTE l SAFETY INJECTION ACTUATION WITH LOSS OF Revision 28 g ., ENGINEERED SAFEGUARDS AC . January 25,1997 UNIT 2 TOTAL REWRITE INITIALS NOTE: Expect " UNIT 2 SA FEGUARDS MCC SUPPL Y BREAKER TRIP" alarm (CO2F-4-7) when 2BS2-35C breaker is closed.
5.17.11 Close 2B52-35C,2B-32 Alternate, on 2B03 in the " TEST"
, position.
l l
5.17.12 CC Pump Breakers
- b. Place 2P-11 A control switch to " PULLOUT".
- c. Place 2B52-34A,2P-11 A breaker, in the " TEST" position.
- d. Close 2P-11 A breaker with the control switch.
5.17.13 Verify Control Room HVAC is operating in Mode 1 (NORMAL) and the " CONTROL ROOM VENTILATION RECIRC MODE" alarm (B-4-9) on C01 is not actuated.
5.17.14 Service water pump alignment: -
- a. Operate P-32C, D and E. :
1
- b. Verify breaker "OPEN" and control switch in " AUTO" for P-32A, B and F.
5.17.15 Two stopwatches are available in the Control Room.
1 Watch # Watch #
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((R ENGINEERED SAFEGUARDS AC January 25,1997 UNIT 2 TOTAL REWRITE INITIALS 5.18 When <15 Minutes to Test Time:
5.18.1 With 1P-29, Unit I turbine driven AF pump, operable, verify shut the P-38A&B pump discharge MOVs and place their control switches in " AUTO". ,
AF-4020, P-38B to 2HX-1B AF-4021, P-38B to IPX-1B AF-4022, P-38A to 2HX-1 A !
I AF-4023, P-38A to 1HX-1 A i
5.18.2 Air compressor alignment:
- a. Operate K-2A compressor in " CONSTANT".
- b. Operate K-3A SA compressor.
5.18.3 Operate W-13B1 Control Room recire fan with W-13B2 selected as backup.
l
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5.18.4 Operate W-85, PAB Battery Room vent fan, in fast speed. l 5.18.5 Stop 2P-707A,2RE-211/212 sample pump.
5.18.6 Stop Unit 2 purge supply and exhaust fans. Leave purge supply and exh::ust valves open. .
1 5.18.7 Start 2W-1 A1 and IBl VNCC fans. Leave remaining VNCC fans secured.
5.18.8 Restore safeguards tests switches to Normal per ICP 10.22A l
and ICP 10.1 J 1&C 5.18.9 Permission to Perform Test l
~
The preparations per test Sc: tion 5.0 are complete. The conditions required by this test are consistent with required ;
plant conditions, including equipment operability. Permission l is granted to perform this test. I DSS TIME DATE' Page 31 of145 CONTINUOUS USE e
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NUCLEAR POWER BUSINESS UNIT ORT 3 OPERATIONS REFUELING TESTS MAJOR IPTE SAFETY INJECTION ACTUATION WITH LOSS OF Revision 28 3
,4 ENGINEERED SAFEGUARDS AC January 25,1997 UNIT 2 ' TOTAL REWRITE TEST SPECIAL INSTRUCTIONS / CLARIFICATIONS AND ERRATA SHEET (S) ;
NOTE: List here any clarification ofprocedure steps and any obvious typographical errors that DO NOTrequire a temporaryprocedure change. Each line item herein listed must be -
approved by the test coordinator and the test director. Add additionalpage(s) as required.
f l
l l
l l
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! NUCLEAR POWER BUSINESS UNIT ORT 3 I OPERATIONS REFUELING TESTS MAJOR :
l IPTE i SAFETY INJECTION ACTUATION WITH LOSS OF Revision 28 '
i< ENGINEERED SAFEGUARDS AC January 25,1997 '
UNIT 2 TOTAL REWRITE :
INITIAlf 6.0 PROCEDURE f
NOTE: Number (s) at the step sign-offspace indicate the test station All responsiblefor the step. Reference Attachment Gfor test :
station / operator assignment.
6.1 Just Prior to the Test 6.1.1 Verify personnel are stationed for the test: 1 -
NOTE: The responsibilityfor the performance of ,
RMP-172for G01 and G02 and the assignment of l testpersonnel is the responsibility of the MTN group.
Test Director (SRO) 1 2CO3 and 2C04 (OPS) 2 C01,left half (OPS) 3 4 C01, right half (OPS) 4 l CO2, G01 and G03 (OPS) 5 CO2, G02 and G04 (OPS) 6 C-59,2B-42 and C-180 (OPS) 7 l 2B-32, and 2P-10 A&B (OPS) 8 l
SA-1, SA-10,2MS-2017 and 2018 (OPS) 9 l IA/SA Compressor, G01 & G02, G03 & G04 (OPS) 10 l CSR Breakers (MTN) 11 2B-391,2A05 and 2A06 UV relays (MTN) 12 Battery charger contactor 2B-4212B and C-22 (MTN) 13 Control R.oom (MTN) 14 NOTE: Recorder operator on station 15 must log the step number clearly on the chart at the start ofevery 1 recording sequence on each recorder.
SI relay racks and CSR recorder (I&C) 15 2P-14 and 2P-15 pumproom (OPS) 16 C01,2C03, and RWST level (OPS) 17 l
! 6.1.2 Verify no reactor trip signals, then reset (close) the reactor trip breakers 2-52/RTA and 2-52/RTB. . 2 Page 33 of145 CONTINUOUS USE
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t NUCLEAR POWER BUSINESS UNIT ORT 3 OPERATIONS REFUELING TESTS MAJOR IPTE SAFETY INJECTION ACTUATION WITH LOSS OF Revision 28
,. ENGINEERED SAFEGUARDS AC January 25,1997 UNIT 2 TOTAL REWRITE INITIALS 1
6.1.3 Open the following valves and leave controllers in
" MANUAL":
l 2CS-466, main feed regulator 2 2CS-476, main feed regulator 2 2CS-480, feed regulator bypass 2 2CS-481, feed regulator bypass 2 6.1.4 Verify or place the following control switches in " AUTO":
2P-15A HHSI Pump 4 2P-10A LHSIPump 2 2P-14A Spray Pump 4 P-32A SW Pump 3 P-32B SW Pump 3 P-32F SW Pump 3 6.1.5 Place IP-4A, boric acid transfer pump, to " PULLOUT" as it is i
Unit 2 Train A powered. Verify IP-4B is in " AUTO". DSS l l
6.1.6 Record 2T-13, Unit 2 RWST, water level.
per 2LI-972. % 17 1
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9
NUCLEAR POWER BUSINESS UNIT ORT 3 OPERATIONS REFUELING TESTS MAJOR l IPTE l SAFETY INJECTION ACTUATION WITH LOSS OF Revision 28
- g. ENGINEERED SAFEGUARDS AC January 25,1997 UNIT 2 TOTAL REWRITE l
INITIALS 1 6.1.7 Responsibilities of Station 17 operat<r l a. Station 17 operator is responsible for the operation of l 2P-10B, the RHR pump not involved in the Train A test, and the pumpback of the refueling cavity to the RWST in order to maximize the available run time of 2P-10A and 2P-15A discharging to the core / refueling cavity. I
- b. The operator must review and understand the alignment of 2P-10B in accordance with test preparatory Section 5.15.
- c. The operator must report all 2P-10B starts and stops to the Test Director and must comply with the motor starting duty limits of Step 2.6 in the Discussion section.
- d. Do not pump back to the RWST to a level greater than that recorded in Step 6.1.6 minus 5% to preclude pumpdown into the reactor vessel or loss of 2P-10B suction.
I
- e. Notify the Test Director if RWST level decreases j to <20%.
l
- f. Station 8 operator is responsible for 2P-10B flow '
adjustment using 2RH-742B as determined by Station 17 operator. 8 l
- g. Station 17 annotation to steps performed by other station operators is informational. The action performed by others in that step will change the flow rate to the refueling cavity and may require a corresponding response from Station 17.
- h. Should Unit I experience an accident condition during the performance of this test, then immediately place 2P-10B control switch to " PULLOUT". 17 l
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l NUCLEAR POWER BUSINESS UNIT ORT 3 OPERATIONS REFUELING TESTS - MAJOR IPTE l
SAFETY INJECTION ACTUATION WITII LOSS OF Revision 28 l (90 ENGINEERED SAFEGUARDS AC January 25,1997 l UNIT 2 TOTAL REWRITE INITIALS 6.1.8 Station 5 operator i
- n. Per DCS 3.1.17 Technical Specifications Interpretation 3.2.2; If normal or standby emergency power for 2A-05 is not available and G-01 is required to operate a level 3 dedicated operator will be required to monitor T-31 A fuel oil level, and dispatch an operator as necessary to manually position valve FO-3930 to maintain the required level of fuel oil in G-Ol's day tank, T-31 A.
- b. Assign Station 5 operator as the level 3 dedicated operator for T-31 A level until G02 is retumed to standby operation per Attachment I. 5, DSS l 6.1.9 Enter a 7-day LCO for P-32F SW pump unavailability during portions of the Train A test in accordance with DCS 3.1.7, Service Water Pump Operability. DSS i
)
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. NUCLEAR POWER BUSINESS UNIT ORT 3 OPERATIONS REFUELING TESTS MAJOR IPTE SAFETY INJECTION ACTUATION WITH LOSS OF Revision 28 p ,. . ENGINEERED SAFEGUARDS AC January 25,1997 UNIT 2 TOTAL REWRITE INITIALS ,
6.2 Loss of AC Followed By Automatic Safety Iniection (Train A) 6.2.1 Public Address Announcement:
I
- a. MESSAGE: " Attention all personnel, attention all personnel; the control room will be conducting a test of the Unit 2 emergency safeguards system with a loss of offsite power. The test will commence in seconds."
Repeat a second time. I
- b. Open 2SI-866A 4
- c. Open 2SI-860A&B 4
- d. Commence a countdown, over the Gai-tronics, to start the G01, G02 and CSR recorders. 1,15, RMP l
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NUCLEAR POWER BUSINESS UNIT ORT 3 !
OPERATIONS REFUELING TESTS MAJOR
- IPTE !
SAFETY INJECTION ACTUATION WITH LOSS OF Revision 28 ,
f" ENGINEERED SAFEGUARDS AC January 25,1997 UNIT 2 TOTAL REWRITE ,
INITIALS NOTE: Step 6.2.2 and 6.2.4 require close coordination between the 4,6 i CO2 station operator and the operator unblocking SI.
i NOTE: In Step 6.2.3, RMP 172 operators are to determine at what RMP point in the countdown the G01 & G02 starting air motors receive the start signal. Ifit isfrom the UVcircuit, it will
\
occur between T(0) -4 seconds and T(0). Ifit isfrom the SI l signal, it will occurfrom T(0) to ~T(0) + 2 seconds. j NOTE: G02 recorder may be stopped when G02 has started and RMP 2A52-67, G02 to 2A05 output breaker, is closed. G01 recorder may be stopped at T(0) + 10 seconds.
NOTE: Test operators 5 and 6 are to record the length of time each 5,6 emergency dieselis operated in an unloaded condition. b i
NOTE: The SI sequence time delay values listed are nominal 1,2,3,4 setpoint values. The actualtime delay values are determined ;
from the G01, G02 and CSR recorders.
6.2.2 At time T(0) +4 seconds, de-energize bus 2A05 by ;
simultaneously depressing the test pushbuttons for UV relays i
2-271/A05 and 2-272/A05 at 2A00-72. Release the test i pushbuttons as soon as 2A52-76,2A05 normal supply breaker, trips open. 12 6.2.3 Record countdown time at which G01 and G02 starting air motors receive a start signal.
G01 RMP G02 RMP 6.2.4 At time T(0) and providing 2A52-76 breaker tripped open, initiate a Train A auto SI signal by unblocking SI using Train A UNBLOCK switch only. 4,6 6.2.5 At time T(0), observe:
- a. 2P-15A breaker close. 4
- b. 2W-1 A1 and 181 trip. 4 Page 38 of145 CONTINUOUS USE
NUCLEAR POWER BUSINESS UNIT ORT 3 OPERATIONS REFUELING TESTS MAJOR IPTE '
SAFETY INJECTION ACTUATION WITH LOSS OF Revision 28
_ ENGINEERED SAFEGUARDS AC January 25,1997 UNIT 2 TOTAL REWRITE INITIALS 6.2.6 At time T(0) +5 seconds, observe 2P-10A start. 2 6.2.7 At time T(0) +10 seconds, observe:
- a. P-38A start. 3
. b. AF-4022, AF to 2HX-1 A, auto open. 3 j 1
6.2.8 At time T(0) +15 and 20 seconds, observe the sequential start l
4 of P-32A, and P-32B SW pumps respectively 3 j 6.2.9 At time T(0) + 25 seconds:
- a. Observe P-32F SW pump start, and 3
- b. Simultaneously start 2P-14A spray pump. 4 l
6.2.10 At time T(0) +40-50 seconds, observe restart of 2W-1 A1 and 1B1, respectively. 4 6.2.11 At time T(0) +90 seconds:
1
- a. Stop the CSR recorder. 15 I
- b. Start 2P-10B for refueling cavity pumpback. 17 6.2.12 Check the status of the following:
NOTE: The checks in this step may beperformed 1 concurrently or out ofthe sequence listed.
l
- b. Reactor trip breakers:
2-52/RTA open 2 2-52/RTB open . 2 Page 39 of145 CONTINUOUS USE e
NUCLEAR POWER BUSINESS UNIT - ORT 3 ,
OPERATIONS REFUELING TESTS MAJOR IPTE SAFETY INJECTION ACTUATICc4 WITH LOSS OF Revision 28 g37 ENGINEERED SAFEGUARDS AC January 25,1997 UNIT 2 TOTAL REWRITE INITIALS
- c. Following safeguards MOVs open 2SI-852A, A Train core deluge 4 2SI-878D, SI to Loop A cold leg 4 2SW-2907, SW return from VNCC 3
- d. Component Cooling AOVs shut:
2CC-LW63, Radwaste system CC supply 2 2CC-LW64, Radwaste system CC return 2
- e. Main feed pumps and valves:
2P-28A, main feed pump, breaker open 2 2P-28B, main feed pump, breaker open 2 l 2CS-466, MFRV, shut 2 2CS-476, MFRV, shut I 2
- f. 480 volt equipment and lockout relays:
2-86/B03 lockout tripped 4 2-86/B04 lockout not tripped 4 2B52-34A,2P-11 A breaker open 2 2B52-35C,2B-32 Alt. remains closed 11 2B52-36C,2B-39 breaker remains closed 11 2B52-38B,2B-32 breaker remains closed 4 2B52-40B,2X-13 breaker remains closed 6 i
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NUCLEAR POWER BUSINESS UNIT ORT 3 OPERATIONS REFUELING TESTS MAJOR IPTE SAFETY INJECTION ACTUATION WITH LOSS OF Revision 28
, ' / ,9 ENGINEERED SAFEGUARDS AC January 25,1997 UNIT 2 TOTAL REWRITE INITIALS
- g. Control Room HVAC at C-67:
VNCSR-4850, CSR outside air damper shut 4 VNCR-4849C, Computer Room outside air damper shut 4 W-13B1 tripped on UV with white light lit above control switch 4 W-13B1 UV white light lit on breaker 2B52-328H. 8
- h. Battery charger supply contactors:
1 2B42-391 open 4 l 2B42-394 open 4 2B42-491 remains closed 4 I
- 2B42-4212B remains closed 4
- i. EDGs and breakers:
- 1. G01 starts 5
- 2. G02 starts 6 l
- 3. G03 does not start 5
- 4. G04 does not start 6
- 5. 2A52-76,2A05 normal supply breaker, open 6
- 6. 2A52-67, G02 to 2A05 supply breaker, closed 6
- 7. Record G02 KW load. KW 6 l
Page 41 of145 CONTINUOUS USE
NUCLEAR POWER BUSINESS UNIT ORT 3 OPERATIONS REFUELING TESTS MAJOR IPTE SAFETY INJECTION ACTUATION WITH LOSS OF Revision 28
- g. , ENGINEERED SAFEGUARDS AC January 25,1997 UNIT 2 TOTAL REWRITE INITIALS
- j. Receipt of alarms / warning lights:
NOTE: Alarm in 1 below and warninglightin 2 below willinitiallyfunction, but should clear as SWpumps are sequenced on. ;
- 1. " UNIT 2 CONTAINMENT RECIRC COOLERS l WATER FLOW LOW" alarm on C01. (C-2-9) 4
- 2. Containment vent cooler low water flow waming l light on C01 benchboard section is illuminated for all coolers with SW flow <1020 gpm. 3
- 3. " UNIT 2 CONTAINMENT VENTILATION ISOLATION" alarm on C01. (C-2-8) 4 ;
l
- 4. " UNIT 2 CONTAINMENT ISOLATION" alarm on 1 C01. (C-2-7) 4
- 5. "70% LEVEL /SI LOCKOUT" warning light !'
illuminated on 2C03 for:
Feedwater Loop A 2 Feedwater Loop B 2
- 6. " UNIT 2 4.16 KV BUS UNDERVOLTAGE" alarm on C02 (F-1-4). 6 !
- 7. " UNIT 2 480 V UNDERVOLTAGE" alarm on CO2 (F-2-7) 6
- k. W-85, PAB Battery Room vent fan, shifts to slow speed.
(W-86 standby fan may operate until low flow alarm clears.) 13
^
l 2017A, supply SOV shuts (unlatched) 9 l 2017B, supply SOV remains open (latched) 9 '
2017C, exhaust SOV opens (unlatched) . 9 l 2017D, exhaust SOV remains shut (latched) 9 Page 42 of145 CONTINUOUS USE
NUCLEAR POWER BUSINESS UNIT ORT 3 OPERATIONS REFUELING TESTS MAJOR !
IPTE SAFETY INJECTION ACTUATION WITH LOSS OF Revision 28 ;
4h ENGINEERED SAFEGUARDS AC January 25,1997 UNIT 2 TOTAL REWRITE INITIALS j
i 2018A, supply SOV shuts (unlatched) 9 2018B, sq ply SOV remains open (latched) 9 j 2018C, exhaust SOV opens (unlatched) 9 i 2018D, exhaust SOV remains shut (latched) 9 l
- n. Radwaste Steam AOVs: l SA10, RS sapply trip valve shut 9 sal, RS PCV shut (must look at the local VPI and not the controller) 9
- o. Accumulator discharge MOV open contactor status:
2B52-324F,2SI-841 A energized 8
- p. CIVs on Isolation Panels A and B:
l Position 2RM-3200B Open 4 2SC-966C Shut 4 2IA-3048 Shut 4 l
2RM-3200C Shut 4 2RM-3200A Shut 4 2MS-2083 Shut 4 2MS-2084 Shut 4 2SC-955 Shut 4 2IA-3047 Shut 4 Page 43 of145 CONTINUOUS USE j
NUCLEAR POWER BUSINESS UNIT ORT 3 OPERATIONS REFUELING TESTS MAJOR IPTE SAFETY INJECTION ACTUATION WITH LOSS OF Revision 28 7 ., ENGINEERED SAFEGUARDS AC January 25,1997 UNIT 2 TOTAL REWRITE INITIALS Position 2CV-313A Open 4 l
2CV-371 A Open 4
- 2WG-1787 Open 4 ,
2CC-769 Shut 4 2CV-315 Shut 4 2CV-371 Shut 4 2MS-5959 Shut 4 2MS-5958 Shut 4 2WG-1786 Shut 4 !
2VNPSE-3245 Open 4 :
2VNPSE-3213 Open 4 2WL-1728 Open 4 2SC-966A Shut 4 2SC-966B Shut 4 2VNPSE-3244 Shut 4 2VNPSE-3212 Shut 4 2WL-1723 Shut 4 -
2SC-951 Shut 4 2SC-953 Shut 4 2RC-508 Shut 4 l 2RC-539 Open 4 l 2WG-1789 Open 4 l 2SI-846 Shut 4 l 2WL-1721 Open 4 l l
2CV-1296 Shut 4 2RC-538 Shut 4 2WG-1788 Shut 4 1 2WL-1698 Shut 4 2WL-1003A Shut . 4 2WL-1003B Shut 4 Page 44 of145 CONTINUOUS USE
NUCLEAR POWER BUSINESS UNIT ORT 3 OPERATIONS REFUELING TESTS MAJOR i IPTE
- SAFETY INJECTION ACTUATION WITli LOSS OF Revision 28
/ ENGINEERED SAFEGUARDS AC January 25.1997 UNIT 2 TOTAL REWRITE '
INITIALS
- q. Check Unit 14160 volt bus fast transfer inhibited with the following control circuit continuity checks:
- 1. For the control circuit of 1 A52-37, I A03 to I A01 bus tie, measure: '
(a) 0 Vdc to ground at TB6C-9 of 2C-157.
Record voltage. Vdc 15 (b) ~ -67 Vdc to ground at TB6C-10 of 2C-157.
Record voltage. Vdc 15 l
- 2. For the control circuit of 1 A52-55,1 A04 to I A02 bus tie, measure:
(a) 0 Vdc to ground at TB6D-1 of 2C-157.
Record voltage. Vdc 15 -
(b) ~ -67 Vdc to ground at TB6D-2 of 2C-157.
Record voltage. Vdc 15
- r. Check condensate pump trip circuit is not inhibited with the I following CPA circuit continuity check:
i l 1. Remove safeguards test lamp No. 861 " Containment Pressure Containment Isolation" in 2C-157. 15
- 2. Connect positive lead of VOM to test point TP-23 and the negative lead to terminal 10 of terminal strip PW in 2C-157. I5
- 3. Record ~ -67 VDC. VDC 15 l
NOTE: Do not install test lamp until required by procedure. 15 l 4. Remove VOM test leads from terminal 10 of terminal strip PW and from TP-23. 15 l
Page 45 of145 CONTINUOUS USE
NUCLEAR POWER BUSINESS UNIT ORT 3 OPERATIONS REFUELING TESTS MAJOR IPTE j SAFETY INJECTION ACTUATION WITH LOSS OF Revision 28 i
g4f ENGINEERED SAFEGUARDS AC January 25,1997 UNIT 2 TOTAL REWRITE INITIALS 6.2.13 At time T(0) +7 minutes (or greater):
l NOTE: Seven minutes allows two minutesfor load 1 sequencing, andfive minutes offullload ;
operation.
- b. Reset (but do not Block) Train A SI. 4
- c. Record Train A LHSI flow per 2FI-626. apm 2
NOTE: Remaining substeps may beperformed I concurrently.
i
- f. Reset 2-86/B03 lockout relay. 4 i l
- g. Observe " UNIT 2 SAFEGUARDS RESET BYPASS ACTIVATED" light for Train A is illuminated (rear of
- C01). 4
- h. Observe presence of" UNIT 1 OR 2 Si TRAIN RESET I
BYPASS ACTIVATED" alarm on C01. (A-3-6). 4
- i. Observe Control Room vent system remains in Mode 2 (recirculation). 4
- j. Locally open 2B52-35C,2B-32 alternate breaker, then rack out the breaker. I1 l k. Reset the "SI/UV" status light on C22, PAB Battery Room l ventilation panel, and observe W-85 fan shift to fast speed.13
r
NUCLEAR POWER BUSINESS UNIT ORT 3 ,
OPERATIONS REFUELING TESTS MAJOR IPTE SAFETY INJECTION ACTUATION WITH LOSS OF Revision 28 i g,,.s. ENGINEERED SAFEGUARDS AC January 25,1997 ;
UNIT 2 TOTAL REWRITE INITIALS
- m. Check condensate pump trip circuit is inhibited with the following CPA circuit continuity check:
- 1. Connect positive lead of VOM to test point TP-23 and the negative lead to terminal 10 of terminal strip PW !
in 2C-157. 15
- 2. Record - 0 VDC. VDC 15
- 4. Install test lamp in 2C-157 cabinet socket No. 861,
" Containment Pressure Containment Isolation". Installer 15 Verifier 15 i
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1 i
i h
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NUCLEAR POWER BUSINESS UNIT ORT 3 1
OPERATIONS REFUELING TESTS MAJOR IPTE ,
, SAFETY INJECTION ACTUATION WITH LOSS OF Revision 28 l tr .in ENGINEERED SAFEGUARDS AC January 25,1997 UNIT 2 TOTAL REWRITE INITIALS 6.3 Test of G02 Automatic Load Sheddine and Restoration NOTE: Steps 6.3.1 through 6.3.5 may beperformed concurrently 1 andin any order.
NOTE: Breakers 2BS2-33C,39C and 40C must be 11 operatedlocally, as required.
- CAUTION
- THE CONTROL SWITCH MUST BE IN 2,4,6,11
" PULLOUT" FOR ALL BREAKER REPOSITIONING IE., TEST, RACK-IN, ,
RACK-OUT. ;
l 6.3.1 Position the following 2003 breakers:
2B52-33C Multi-Arnp Test & Closed 11 2B52-34A 2P-1l A Test & Closed 2 i 2B52-36B 2T-1C Test & Closed 2 )
2B52-37A 2P-2A Test & Closed 2 l 2B52-37B 2P-2B Test & Closed 2 2B52-37C B-33 Rackin & Closed 4 2B52-38C 2B-31 Rack In & Closed 4 2B52-39C 2B01 bus tie Test & Closed 6,11 l
2B52-40C 2B04 bus tie Test & Closed
- 6,11 ;
- Insen control power fuses.
6.3.2 Verify 480 and 4160 V UV alarms on CO2 cleared. l (F-1-4 & F-2-7) 6 6.3.3 2B03 lockout relay:
- a. Remove power to lockout relay by opening MOB-158 in C01. 14 i l
- b. Check receipt of" UNIT 2 COMMON CRITICAL CONTROL POWER FAILURE" alarm on C02 (F-4-1) 6 I
- c. Verify white power available light for 2-86/B03 on rear of C01 is de-energized. 4 1
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NUCLEAR POWER BUSINESS UNIT ORT 3 OPERATIONS REFUELING TESTS MAJOR I IPTE I SAFETY INJECTION ACTUATION WITH LOSS OF Revision 28 p, % ENGINEERED SAI EGUARDS AC January 25,1997 ;
UN?T 2 TOTAL REWRITE i INITIALS
- CAUTION
- THE CONTROL SWITCH MUST BE IN 6,12
" PULLOUT" FOR ALL BREAKER REPOSITIONING IE., TEST, RACK-IN, RACK-OUT.
NOTE: Reference P&L 3.2for 2A 05 breakers in " TEST". 1,12 6.3.4 Place 2A52-76,2A03/2A05 bus tie in the " TEST" and
" CLOSED" condition. 6,12 6.3.5 Stop 2P-15A, then place control switch to " AUTO" and verify 2P-15A does not auto start. 4,17 NOTE: Countdown to start CSR recorder required. 1,15 6.3.6 Place the control switch for 2A52-67, G02 to 2A05 breaker to
" PULLOUT". 6
6.3.7 Observe
I
- a. 2A52-76,2A03/2A05 bus tie, open. 6
)
I
- b. Auto closure of 2P-15A breaker. 4
- c. P-38A trip, then restart. 3
- d. Stop CSR recorders after P-38A restart or 30 seconds after recorder start. 15
- e. Following breakers not trinned:
2B52-34A 2P-ll A 2 2B52-36C 2B-39 11 2B52-38B 2B-32 4 2B52-40B 2X-13 6 l l
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NUCLEAR POWER BUSINESS UNIT ORT 3 OPERATIONS REFUELING TESTS MAJOR IPTE l
SAFETY INJECTION ACTUATION WITH LOSS OF Revision 28 l c) "" ENGINEERED SAFEGUARDS AC January 25,1997
! UNIT 2 TOTAL REWRITE l
INITIALS
- f. Following breakers trinned:
2B52-33C Multi-Amp 11 2B52-34B P-32F 3 2B52-36A 2P-10A 2,17 2B52-36B 2T-lC 2 2B52-37A 2P-2A 2 2B52-37B 2P-2B 2 2BS2-37C B-33 4 2B52-38A 2P-14A 4 2B52-38C 2B-31 4 2B52-39A 2W-1A1 4 2B52-39B 2W-1B1 4 2B52-39C 2B01 bus tie 6 2B52-40C 2B04 bus tie 6 6.3.8 Close MOB-158 in C01. 14
6.3.9 Observe
l l
- a. 2-86/B03 lockout relay trip. 4
- b. 2B52-34A,2P-11 A breaker trip. 2 l
l
- c. Check " UNIT 2 COMMON CRITICAL CONTROL l' POWER FAILURE" alarm on CO2 cleared. (F-4-1). 6 6.3.10 Green flag 2P-14A control switch. ~ 4 6.3.11 Position 2RH-614 to full open. 2 NOTE: Recorder may be secured after auto reclas::re of2 W-1A1 15 and 181 breakers.
l 6.3.12 Start CSR recorder. 15 l 6.3.13 Place 2A52-67 control switch to " AUTO" and observe breaker closure. 5 Page 50 of 145 CON? INUOUS USE
NUCLEAR POWER BUSINESS UNIT- ORT 3 OPERATIONS REFUELING TESTS MAJOR IPTE SAFETY INJECTION ACTUATION WITH LOSS OF Revision 28
, ENGINEERED SAFEGUARDS AC January 25,1997 UNIT 2 TOTAL REWRITE INITIALS i !
6.3.14 Approximately 25 seconds after 2A52-67 closure, restart 2P-14A spray pump simultaneous with P-32F start. 4 6.3.15 Observe the sequential restart of:
2P-15A, SI pump 4,17 2P-10A, RHR pump 2,17 P-32F, SW pump Time 3 2W-1 A1, VNCC fan 4 ,
2W-1 B 1, VNCC fan 4 6.3.16 Throttle 2HC-624 for a flow of 200-300 gpm per 2FI-626. 2,17 NOTE: Steps 6.3.17 and 6.3.18 may be performed concurrently. l 6.3.17 Test of degraded grid voltage circuit on short time delay (SI signal present):
- a. Check Unit 2 A Train SI short time delay circuit is functional to I A05:
- 1. At the door of 1 A52-57 on 1 A05, remove the undervoltage test panel cover. 12
- b. Reclose 2A52-76. 6 NOTE: Erpect an ~S second time delayfor breaker trip. 12
- c. Simultaneously depress and hold depressed the trip test push buttons for relays 2-274/A05 and 2-275/A05 until breaker 2A52-76 trips, then release test buttons. 12 l
l d. Observe 2A52-76 breaker open. 6
- e. Reclose 2A52-76. 6 Page 51 of145 CONTINUOUS USE l
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l NUCLEAR POWER BUSINESS UNIT ORT 3 OPERATIONS REFUELING TESTS MAJOR IPTE l SAFETY INJECTION ACTUATION WITH LOSS OF Revision 28
, y. ENGINEERED SAFEGUARDS AC January 25,1997 -
UNIT 2 TOTAL REWRITE INITIALS
- f. Simultaneously depress and hold depressed the trip test push buttons for relays 2-274/A05 and 2-276/A05 until ,
breaker 2A52-76 trips, then release test buttons. 12
- g. Observe 2A52-76 breaker open. 6
- h. Reset UV relay targets for 2-274/A05,2-275/A05, and 2-276/A05. 12
- i. Reclose 2A52-76. 6 !
6.3.18 Test of Train A SW system isolation:
- a. Observe six SW pumps in operation. 3
- b. Record the SW valve number of the SFP HX that is not in service (SW-2930A or B), then open SW-2930A&B.
SW-2930 3
- c. Stop P-32C, D & E SW pumps. Leave control switches in
' " AUTO". 3
- d. Observe the following valves shut: ,
SW-2816, Service Building cooling MOV 3 SW-2930A, spent fuel pool cooling MOV 3 SW-LW61, SW to blowdown evaporator AOV 7 l
- e. Observe the following valves remain open:
2SW-2880, Unit 2 turbine hall supply MOV 3
)
SW-2817, water treatment supply MOV 3 l SW-2930B, spent fuel pool cooling MOV 3 l SW-LW62, SW from blowdown evaporator AOV 7 i
- f. Restart one SW pump. 3 Page 52 of 145 CONTINUOUS USE
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! SAFETY INJECTION ACTUATION WITH LOSS OF ' Revision 28 l . s t. ENGINEERED SAFEGUARDS AC January 25,1997 i UNIT 2 TOTAL REWRITE t
INITIALS
- g. Reopen valves:
SW-2816 3 SW-2930A 3 :
l SW-LW61 7
- i. Restart remaining SW pumps. 3 6.3.19 When Steps 6.3.17 and 6.3.18 are complete:
- a. Reset (but do not Block) Train A SI. 4 ,
- b. At the undervoltage test panel on the door of I A52-57 on l A05, measure and record ~0 VDC from
{
- c. Reset 2-86/B03 lockout relay. 4 NOTE: Steps 6.3.20 and 6.3.21 may beperformed concurrently. 1 ;
6.3.20 Test of degraded grid voltage circuit on long time delay (no SI i i signal)
NOTE: Expect an ~45 second time delayfor breaker trip. 12 l 1
- a. Simultaneously depress and hold depressed the trip test push buttons for relays 2-274/A05 and 2-275/A05 until breaker 2A52-76 trips, then release test buttons. 12
, b. Check receipt of" UNIT 2 4.16 KV BUS UNDERVOLTAGE" alarm on CO2 (F-1-4). 6 l
- c. Observe 2A52-76 breaker open. 6
- d. Reset UV relay targets for 2-274/A05 and 2-275/A05. 12 l
l
) '
Page 53 of 145 CONTINUOUS USE l .
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NUCLEAR POWER BUSINESS UNIT ORT 3 OPERATIONS REFUELING TESTS MAJOR IPTE SAFETY INJECTION ACTUATION WITH LOSS OF Revision 28 e,, ENGINEERED SAFEGUARDS AC January 25,1997 l UNIT 2 TOTAL REWRITE '
l INITIALS !
- e. Check " UNIT 2 4.16 KV BUS UNDERVOLTAGE" alarm cleared (F-1-4). 6 l
- f. Close 2A52-76. 6 9
- g. Simultaneously depress and hold depressed the trip test buttons for relays 2-274/A05 and 2-276/A05 until breaker ,
2A52-76 trips, then release test buttons. 12
- h. Observe 2A52-76 breaker open. 6
- i. Reset UV relay targets for 2-274/A05 and 2-276/A05. 12
- j. With 2A52-76 control switch in " PULLOUT", rack in 2A52-76. 6,12 6.3.21 Close the following contactors from 2C-20:
- a. 2B42-394, D-107 contactor 4 NOTE: The 2C-20, ASIP operator and a MTN 4,12 electrician at the contactorpanel must communicate to accomplish thefollowing step.
NOTE: To close contactor 2B42-391, hold the 4,12 contactor controlswitch on 2C-20 in "CLOSE" while the electrician closes the contactor manually.
- b. 2B42-391, D-09 contactor 4,12 6.3.22 When Steps 6.3.20 and 6.3.21 are complete, then simulate Unit 1 Train A Si and observe action:
- a. Place 2A52-76 control switch out of" PULLOUT" but do not close 2A52-76. 6 l b. In 2C20 (ASIP), identify slider at TB12-8. Check 14 Concur 4 Pace 54 of145 CONTINUOUS USE
t NUCLEAR POWER BUSINESS UNIT ORT 3 i OPERATIONS REFUELING TESTS Mr?OR IPTE SAFETY INJECTION ACTUATION WITH LOSS OF Revision 28
/!kfM ENGINEERED SAFEGUARDS AC January 25,1997 UNIT 2 TOTAL REWRITE l INITIALS i
- c. Open slider at TB12-8. 14 ,
- d. Observe contactors 2B42-391 and 2B42-394 t.ip open. 4
- e. Reclose slider TB12-8. 14
- f. Independent verification of closed slider TB 12-8. 4 6.3.23 When >l5 minutes have elapsed since the time recorded in Step 6.3.15, then stop 2P-15A and place control switch to
" PULLOUT".
4,17 6.3.24 Stop the following G02 loads and return the control switch to
" PULLOUT":
2P-10A 2,17 l 2P-14A 4 6.3.25 Transfer 2A05 load from G02 to 2A03 per Attachment D. 6 6.3.26 Adjust 2RH-742B as required to reduce flow and preclude l stopping 2P-10B on low cavity level. 8,17 6.3.27 Open 2RH-624. 2 l
l l
l Page 55 of145 CONTINUOUS USE
NUCLEAR POWER BUSINESS UNIT ORT 3 OPERATIONS REFUELING TESTS MAJOR IPTE l SAFETY INJECTION ACTUATION WITH LOSS OF Revision 28 1
- , ENGINEERED SAFEGUARDS AC January 25,1997 UNIT 2 TOTAL REWRITE INITIALS 6.4 Test of Unit 2 A Train Loss of AC with Si and G01 6.4.1 Enter a 7-day LCO for the unavailability of an emergency power source to 1 A05 and 2A05. DSS l
NOTE: Should Unit 1 experience a loss ofoffsitepower and/or 1,5 an SI actuation, then restore G01 to IA05 by (in order) placing 2A52-73 controlswitch to " PULLOUT" and 1A52-60 '
controlswitch to "A UTO".
I 6.4.2 Place 1 A52-60, G01 to 1 A05, breaker control switch to i
" PULLOUT". 5 !
6.4.3 Alignment of G01 to 2A05
- a. On CO2, place the G02 normal output breaker control switch "2A52-67, G02 DIESEL GENERATOR TO BUS l 2A05 BREAKER," to " PULLOUT". 6
- b. Locally at C35A, place the G02 normal output l
breaker control switch "2A52-67, G02 TO 2A05," to ;
" PULLOUT". 10 l L
- CAUTION
- ENSURE THAT THE CONTROL 5,6 l SWITCHES FOR BREAKERS 2A52-73 !
(G01) AND 2A52-67 (G02) ARE NOT PLACED IN " AUTO" AT THE SAME TIME.
- c. On CO2, unlock (key 43) and place the G01 alternate output breaker control switch "2A52-73, G01 DIESEL GENERATOR TO BUS 2A05 BREAKER," to " AUTO". 5 6.4.4 Place 2P-15A control switch to " AUTO" and verify 2P-15A does not auto start. Place 2P-14A control switch to " AUTO". 4 NOTE: Step 6.4.6 must be initiated before G0111.5 minute 1 cooldown timer expires or an unnecessaryfast restart will occur.
6.4.5 Commence a shutdown of G01 per Attachment F. 5 l Page 56 of145 CONTINUOUS USE l'
i NUCLEAR POWER BUSINESS UNIT ORT 3 j OPERATIONS REFUELING TESTS MAJOR 1 IPTE l
SAFETY INJECTION ACTUATION WITH LOSS OF Revision 28 ;
ENGINEERED SAFEGUARDS AC January 25,1997 UNIT 2 l TOTAL REWRITE l INITIALS i
NOTE: Countdown required to start CSR recorder. Recorder 1,15 may be stopped 90 seconds after Step 6.4.6.
NOTE: Manual restart of2P-14A required coincident with auto 4 :
restart ofP-32F. l 6.4.6 When >15 minutes have elapsed since the time recorded in )
Step 6.3.15, then initiate a 2A05 and 2B03 loss of AC and SI '
reinitiation by placing the control switch for 2A52-76,2A03 to l 2A05 bus tie, to " PULLOUT". 6 1
6.4.7 Observe
- a. P-32F and P-38A trip. 3 l
- b. 2W-1 A1 and IBl trip. 4 1 i
- c. 2P-15A breaker close on a dead bus. 4,17
- d. G01 return to speed and voltage. 5 l l
- e. 2A52-73 close. 5 l 6.4.8 Observe or perform G01 load sequencing in following order: )
- a. 2P-10A starts 2,17
- b. P-38A restarts 3
- c. P-32F restarts, then simultaneously restart 2P-14A. 3,4
- d. 2W-1 A1 restarts 4
- e. 2W-1B1 restarts Time 4 j l
- f. Record G01 KW load KW 5
- 6.4.9 When >90 seconds after the restoration of power to 2A05 and 2B03, then reset (but do not block) Train A SI. . 4 i
l i
l-Page 57 of145 CONTINUOUS USE
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NUCLEAR POWER BUSINESS UNIT ORT 3 ,
OPERATIONS REFUELING TESTS MAJOR :
- SAFETY INJECTION ACTUATION WITH LOSS OF Revision 28 l g , ,. ENGINEERED SAFEGUARDS AC January 25,1997 i UNIT 2 TOTAL REWRITE l INITIALS NOTE
- Countdown to start CSR recorder required. 1,15 NOTE: 2P-lM controlswitch must be greenflagged before 4 manually closing breaker.
6.4.10 When >15 minutes from the time recorded in Step 6.4.8, then place 2A52-73, G01 to 2A05, breaker control switch to
" PULLOUT", and four seconds later return the control switch to " AUTO" smartiv. 5 6.4.11 Observe / perform: '
- a. 2P-15A breaker remains closed. 4
- b. 2P-10A restarts 2
- c. P-38A restarts 3 i
- d. P-32F restarts, then simultaneously restart 2P-14A 3,4
- e. 2W-1 A1 and 2W-1B1 restart Time 4 6.4.12 Throttle 2HC-624 for a flow of 200-300 gpm per 2FI-626. 2,17 i
NOTE: During the next step, hold at each holdpointfor I&C 1,15 to check MG-6 relay latching clearance.
6.4.13 When >90 seconds after the restoration of power to 2A05 and 2B03:
Page 58 of145 CONTINUOUS USE
NUCLEAR POWER BUSINESS UNIT ORT 3 OPERATIONS REFUELING TESTS MAJOR IPTE i SAFETY INJECTION ACTUATION WITH LOSS OF Revision 28 sy, f
ENGINEERED SAFEGUARDS AC January 25,1997 !
UNIT 2 TOTAL REWRITE INITIALS -
NOTE: Perform Steps 6.4.13.c, d and e, of Train A 1,15 ;
SLA-A and/orSIA-B latch clearance was adjusted ,
in Step 6.4.13.a. Otherwise NA Steps 6.4.13.c, d and e.
- c. Unblock Train A SI. 4
- e. Reset Train A SI. 4 .
NOTE: Perform Step 6.4.13.fofFA-1 and/or 1,15 FA-2 latch clearance was adjusted in Step 6.4.13.b. Otherwise NA Step 6.4.13.f
6.4.14 Stop the following G01 loads by placing the control switch to
" PULLOUT":
i 2W-1A1 ~4 l
2W-1B1 4 6.4.15 Shut AF-4022 and leave AF-4022 control switch in the manual mode of operation. 3 6.4.16 Reset UV relay targets for UV relays 2-271,272,273,274, 275, and 276/A05 as required. 12 NOTE: Steps 6.4.20 through 6.4.26 may beperformed concurrently 1 with Steps 6.4.17 throngh 6.4.19.
6.4.17 Transfer 2A05 load from G01 to 2^03 per Attachment D. 5 Page 59 of145 CONTINUOUS USE
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l NUCLEAR POWER BUSINESS UNIT ORT 3 f' OPERATIONS REFUELING TESTS MAJOR IPTE SAFETY INJECTION ACTUATION WITH LOSS OF Revision 28
! t. ENGINEERED SAFEGUARDS AC January 25,1997 i l UNIT 2 TOTAL REWRITE ;
INITIALS l
( !
l 6.4.18 Alignment of G02 to 2A05:
l l a. On C02, place the G01 alternate output breaker control l
switch "2A52-73 G01 DIESEL GENERATOR TO BUS
! 2A05 BREAKER," to " PULLOUT" and enable mechanical
- lock. 5
- CAUTION
- ENSURE THAT THE 5,6 CONTROL SWITCHES FOR l BREAKERS 2A52-73 (G01)
AND 2A52-67 (G02) ARE NOT PLACED IN " AUTO" AT THE SAME TIME.
- b. On CO2, place the G02 normel culput breaker control switch "2A52-67 G02 DIESEL GENERATOR TO BUS 2A05 BREAKER," to " AUTO". 6
- c. Locally at C35A, place the G02 normal bus control switch "2A52-67 G02 to 2A05," to " AUTO". 10 6.4.19 When 2A52-73 breaker is open, then place 1 A52-60 breaker control switch to " AUTO". 5
- 6.4.20 Exit 7-day LCO for P-32F. DSS l 6.4.21 Reset the following
- a. 2-86/B03 lockout relay 4
- b. Train A CI 4
- c. Train A CVI 2 NOTE: The remaining substeps ofSection 6.4 may beperformedin 1 any order.
6.4.22 Open all CIVs. Verify isolation panels A and B indicate all CIVs open. .. 4 l .
Page 60 of145 CONTINUOUS USE
NUCLEAR POWER BUSINESS UNIT ' ORT 3 OPERATIONS REFUELING TESTS MAJOR IPTE SAFETY INJECTION ACTUATION WITH LOSS OF Revision 28 g, ENGINEERED SAFEGUARDS AC January 25,1997 UNIT 2 TOTAL REWRITE INITIALS NOTE: Reference P&L 3.2for 2A05 breakers in " TEST". 1,12 -
6.4.23 With the control switch in " PULLOUT", place the following breakers in the " TEST" condition: .
2A52-74 2P-15A 4,12 2B52-38A 2P-14A 4,11 6A.24 Shut or verify shut the following HHSI valves:
2SI-866A 4,17 !
2SI-878B 4 I 2SI-878D 4 6.4.25 Shut the following containment spray system valves:
2SI-860A 4 2SI-860B 4 2SI-862G 16 6.4.26 When >15 minutes have elapsed since the time recorded in l
Step 6.4.11, then 1
- a. When 2P-10A is powered from offsite AC, then stop l 2P 10A and place control switch to " PULLOUT". 2
- b. Shut 2SI-856A. 4
- c. Shut 2SI-852A. 4 Page 61 of145 CONTINUOUS USE
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NUCLEAR POWER BUSINESS UNIT ORT 3 ,
OPERATIONS REFUELING TESTS MAJOR IPTE SAFETY INJECTION ACTUATION WITH LOSS OF Revision 28 Mg ENGINEERED SAFEGUARDS AC January 25,1997 UNIT 2 TOTAL REWRITE INITIALS ;
NOTE: Steps 6.4.27 and 6.4.28 may be performed concurrently 1 with test Sections 6.5 and 6.6.
6.4.27 Continue pumping the refueling cavity to the RWST with 2P-10B until RWST level is within 5% of the starting level recorded in Step 6.1.6, then stop 2P-10B and place control switch to " PULLOUT". 17 6.4.28 Post -test recovery of Train A Containment Spray System
- a. Flush the seal area of 2P-14A by spraying the seal area with !
warm DI water. 16 i
- b. Red lock shut 2SI-862G,2P-14A high flow test line isolation.
Red Lock No. 16
- c. Attach a vent hose from 2SI-869A to a local exhaust duct, f then open 2SI-869A and depressurize the discharge header >
to atmospheric pressure. 16 i
Red 1.ock No. 16 l
- e. With DSS concurrence, open and red lock 2SI-868A, containment spray header isolation. Otherwise NA this '
step.
Red Lock No. DSS,16 I
- f. Open and red lock 2SI-874A, Train A eductor suction.
Red Lock No. 16 1
l 1
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L NUCLEAR POWER BUSINESS UNIT ORT 3 OPERATIONS REFUELING TESTS MAJOR '
IPTE SAFETY INJECTION ACTUATION WITH LOSS OF Revision 28
- 1 ENGINEERED SAFEGUARDS AC January 25,1997 UNIT 2 TOTAL REWRITE INITIALS 6.5 Test of Train A Manual SI. Non-Safecuards Load Strinnine. and SW Pumn Seauencine l .
6.5.1 Close reactor trip breakers 2-RTA and 2-RTB. 2 NOTE: Steps 6.5.2 through 6.5.6 may beperformed concurrently I andin any order.
6.5.2 Position the following breaker control switches to " AUTO": .
2P-14A 4 2P-1SA 4 2W-1 A1 4 2W-1B1 4 NOTE: Breakers 2B52-33C, 39C and 40C must be 11 operatedlocally, as required.
NOTE: 2B03 breaker condition, ie., "RA CKED-IN" or 2,4,6,11
" TEST" has been previously established.
6.5.3 Close or verify closed the following 2B03 breakers:
2B52-33C Multi-Amp Test & Closed 11 2B52-34A 2P-11 A Test & Closed 2
, 2B52-36B 2T-1C Test & Closed 2 2B52-37A 2P-2A Test & Closed 2 I 2B52-37B 2P-2B Test & Closed 2 2B52-37C B-33 Rack In & Closed 4 ;
2B52-38C 2B-31 Rack In & Closed 4 2B52-39C 2B01 bus tie Test & Closed u,11 2B52-40C 2B04 bus tie Test & Closed
- 6,11
- Insert control power fuses.
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. . . ENGINEERED SAFEGUARDS AC January 25,1997 UNIT 2 TOTAL REWRITE INITIALS 6.5.4 - Isolate Train B manual Si signal generation from both manual SI push-buttons by opening slider UM-2 on riser 28AB0 in C01. 14 i
Verified 4 6.5.5 When >l5 minutes have elapsed since the time recorded in Step 6.4.11.e, then operate P-32C, D and E, stop P-32A, B and F, and leave all SW pump control switches in " AUTO". Time 3 -
6.5.6 Reposition main feed regulator valves:
- a. Clear at least 3 of 4 low TAVG signals. 15
- b. Open 2CS-466 and 476. 2 NOTE: Step 6.5.8 must be initiated before G01 and G02 1,5,6 11.5 minute cooldown timers expire or an unnecessaryfast restart willoccur.
6.5.7 Commence a shutdown of G01 and G02 per Attachment F: 1 I
- a. G01 5 i
- b. G02 6 NOTE: Countdown required to start CSR recorder. Recorders 1,15 may be stopped 90 seconds after Step 6.5.8.
6.5.8 With G01 and G02 on their cooldown timers, initiate a manual !
SI using the left-hand pushbutton. 4 Page 64 of145 CONTINUOUS USE S
NUCLEAR POWER BUSINESS UNIT ORT 3 OPERATIONS REFUELING TESTS MAJOR IPTE SAFETY INJECTION ACTUATION WITH LOSS OF Revision 28
, ,e ENGINEERED SAFEGUARDS AC January 25,1997 UNIT 2 TOTAL REWRITE INITIALS ,
6.5.9 Observe
RTA breaker open 2 RTB breaker open 2
" MANUAL SI" reactor trip alarm on 2C04 2 2CS-466 shut 2 2CS-476 shut 2 P-38A trip, then sequence restart Time 3 P-32A sequenced start 3 P-32B sequenced start 3 P-32F sequenced start 3 2P-15A breaker closed 4 2W-1 A1 breaker sequenced closed 4 2W-1B1 breaker sequenced closed 4 2-86/B03 lockout tripped 4 2-86/B04 lockout not tripped 4 G01 return to speed and voltage 5 G03 unaffected 5 G02 return to speed and voltage 6 G04 unaffected 6 SIM-A tripped 15 SIM-B not tripped 15 6.5.10 Following 2B03 breakers not trioped:
2B52-34A 2P11A 2 2B52-36C 2B39 11 2B52-37A 2P-2A 2 2B52-37B 2P-2B 2 2B52-38B 2B32 4 2B52-40B 2X13 5 j .
Page 65 of145 CONTINUOUS USE
NUCLEAR POWER BUSINESS UNIT ORT 3 OPERATIONS REFUELING TESTS MAJOR IPTE SAFETY INJECTION ACTUATION WITH LOSS OF Revision 28 g ,
ENGINEERED SAFEGUARDS AC January 25,1997 UNIT 2 TOTAL REWRITE INITIALS -
6.5.11 Following 2B03 breakers tripped:
2B52-33C Multi-Amp 11 2B52-36B 2T-lC 2 !
2B52-37C B-33 4 ;
2B52-38C 2B-31 4 2B52-39C 2B01 bus tie 6 l 2B52-40C 2B04 bus tie 6 6.5.12 Close 2P-14A breaker and observe breaker remains closed. 4 6.5.13 Perform SIM-A latch clearance checks and adjustment. 15 ,
6.5.14 When at least 90 seconds have elapsed since initiation of manual SI, then reset Train A SI. (I&C hold) 4 ;
1 6.5.15 Clear the " MANUAL SI" reactor trip alann on 2C04. 2 l
6.5.16 When >15 minutes have elapsed since the time recorded in Step 6.5.9, then initiate a manual SI using the right-hand l pushbutton. 4 !
6.5.17 Observe:
" MANUAL SI" reactor trip alarm on 2C04 2 P-38A trip, then sequence restart 3 SIM-A tripped (I&C hold) 15 SIM-B not tripped 15 l
l l
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M# ENGINEERED SAFEGUARDS AC January 25,1997 UNIT 2 TOTAL REWR1TE INITIALS )
6.5.18 When at least 90 seconds have elapsed since initiation of manual SI, then:
- b. Reset 2-86/B03 lockout relay 4
- c. Stop P-38A. 3
- d. Open 2P-14A breaker and place control switch to
" PULLOUT". 4 l
- e. Open 2P-15A breaker and place control switch to i
" PULLOUT". 4
- f. Open 2W-1 A1 and 1B1 breakers and place control switches I to " PULLOUT". 4
- h. Stop P-32C,D,&E SW pumps. 3
- i. Open 2P-11 A breaker and place control switch to
" PULLOUT". 2 6.5.19 Train A Test Recovery NOTE: The remaining sub-steps may be l performed concurrently in any order.
- a. G01 and G02 are not involved in the remainder of the test and we to be load tested or secured per Attachment I. G01 ar.1 G02 seven day LCO termination is addressed in Attachment I. 5,6 i
- b. Close slider UM-2 in C01 restoring Train B manual SI capability. 14 Verified 4 4 Page 67 of145 CONTINUOUS USE l
NUCLEAR POWER BUSINESS UNIT ORT 3 OPERATIONS REFUELING TESTS MAJOR IPTE SAFETY INJECTION ACTUATION WITH LOSS OF Revision 28 g .1 ENGINEERED SAFEGUARDS AC January 25,1997 UNIT 2 TOTAL REWRITE INITIALS
- c. Provide a 2 of 4 low AT vasignal. 15
- e. Close the following 2B03 breakers:
2B52-37C, B-33 4 2B52-38C,2B31 supply 4
- f. Remove spare DB-50 breaker from cubicle 2B52-35C in 2B03 and install in the " TEST" position in cubicle 2B52-31B of 2B04. I1
- CAUTION
- THE CONTROL SWITCH 2,4,5,11 MUST BE IN " PULLOUT" FOR ALL BREAKER REPOSITIONING,IE.,
TEST, RACK-IN, RACK-OUT.
- g. Reposition the following 2B03 breakers:
Breaker Number Breaker Condition 2B52-33C Multi-Amp RACKED-OUT 11 2B52-34A 2P-11 A RACKED-IN 2,11 2B52-36B 2T-1C RACKED-OUT 2,11 2B52-37A 2P-2A RACKED-OUT 2,11 2B52-37B 2P-2B RACKED-OUT 2,11 2B52-38A 2P-14A RACKED-OUT 4,11 2B52-39C 2B01 bus tie RACKED-OUT 6,11
- h. Control Room HVAC:
- 1. Shift CR ventilation system to normal mode (Mode 1). 4
- 2. Check VNCSR-4850 and VNCR-4849C have auto re-opened. 4 Page 68 of 145 CONTINUOUS USE
NUCLEAR POWER BUSINESS UNIT ORT 3 OPERATIONS REFUELING TESTS MAJOR IPTE SAFETY INJECTION ACTUATION WITH LOSS OF Revision 28 ENGINEERED SAFEGUARDS AC January 25,1997 UNIT 2 TOTAL REWRITE INITIALS
- 3. Check " CONTROL ROOM VENTILATION RECIRC MODE" alarm on C01 cleared. (B-4-9) 4
- i. Reset W-13B1 UV lockout by depressing the black pushbutton on the door of cub.:cle 2B52-328H, then
- 1. Observe white light go out at the cubicle Sor and 8
- 2. At the W-13B1 control switch on C-67. 4
- 3. Restart W-13B1 and observe W-13B1 remains operating. 4
- j. Reset Train A CVI, then reopen 2VNPSE-3212 and 3244. 2 t
Verify isolation panels A & B indicate all G Vs open. 4
- k. Open SA-10, then verify that SA-1 auto reopens. Must observe local SA-1 VPI versus controller output. 9 NOTE: Reference P&L 3.2for seismic concern of 1,12 2A05 breakers.
- m. W-85/86 fan alignment:
- 1. Reset the "SI/UV" status light on C22, PAB Battery !
Room ventilation panel, and observe W-85 fan shift l to fast speed. 8
- 2. Operate W-86 in fast speed. 8 i
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NUCLEAR POWER BUSINESS UNIT ORT 3 OPERATIONS REFUELING TESTS MAJOR '
IPTE SAFETY INJECTION ACTUATION WITH LOSS OF Revision 28
, ENGINEERED SAFEGUARDS AC January 25,1997 UNIT 2 TOTAL REWRITE ,
INITIALS 6.6 Just Prior to the B Train Test 6.6.1 Return G-04 to service as standby emergency power supply to 2A06:
- a. Enter a 24-hour LCO for P-32D&E SW pump unavailability during portions of the Train B test in accordance with Technical Specification 15.3.3.D.2 and DCS 3.1.7, Service Water Pump Operability. DSS ;
- b. Enter a 7-day LCO for P-38B AF pump unavailability during portions of the Train B test in accordance with l Technical Specification 15.3.4.C.2. DSS l l
- c. Enter a 7-day LCO for unavailability of standby emergency power supply to 2A06. DSS
- d. On C02, place the G-03 alternate output breaker control switch "2A52-87, G-03 DIESEL GENERATOR TO BUS 2A-06 BREAKER", to " PULLOUT" and enable mechanical key lock.
{
5 i
- e. Locally at C81, place the G-03 alternate output breaker ;
control switch "2A52-87, G-03 DIESEL GENERATOR i TO BUS 2A06 BREAKER", to " PULLOUT" and enable ;
mechanical key lock. 10
- CAUTION
- ENSURE THAT THE CONTROL SWITCHES FOR BREAKERS 2A52-87 (G-03) AND 2A52-93 (G-04) ARE NOT PLACED IN " AUTO" AT THE SAME TIME.
- f. On CO2, place the G-04 normal output breaker control switch "2A52-93, G-04 DIESEL GENERATOR TO BUS 2A-06 BREAKER", to " AUTO". 6 l g. Locally at C82, place the G-04 normal output breaker control switch "2A52-93, G-04 DIESEL GENERATOR TO BUS 2A06 BREAKER", to " AUTO". 10 Page 70 of 145 CONTINUOUS USE l .
NUCLEAR POWER BUSINESS UNIT ORT 3 OPERATIONS REFUELING TESTS MAJOR -
IPTE SAFETY INJECTION ACTUATION WITH LOSS OF Revision 28 g.3 ENGINEERED SAFEGUARDS AC January 25,1997 UNIT 2 TOTAL REWRITE !
INITIALS NOTE: Remaining steps in this Section may be performed 1 >
concurrently andin any order.
6.6.2 Main feedwater pumps and valves:
- a. Reset feedwater isolation Loop A and Loop B by depressing 2CS-480 and 481 reset pushbuttons on 2C03.
Verify "70% LEVEL /SI LOCKOUT" warning lights are not illuminated for Loop A and Loop B. 2
- b. Close 2P-28A&B main feed pump breakers. 2
- c. Reset (close) the 2-52/RTA and RTB reactor trip breakers. 2 >
9
- d. Verify main feed AOVs reopen:
2CS-466 2 2CS-476 2 2CS-480 2 2CS-481 2 6.6.3 Verify AF-4020, P-38B to 2HX-1B, is shut with control switch in "AU T0". 3 6.6.4 Operate K-2A and K-2B compressors in " CONSTANT". 4 6.6.5 Operate W-14B Control Room clacoal filter fan by placing l W-14 selector switch to W-14A manual position, then start i W-14B. Verify W-14B remains operating. 4 l
l Page 71 of145 CONTINUOUS USE l
NUCLEA.R POWER BUSINESS UNIT ORT 3 L OPERATIONS REFUELING TESTS MAJOR !
IPTE .
SAFETY INJECTION ACTUATION WITH LOSS OF Revision 28 !
ENGINEERED SAFEGUARDS AC January 25,1997 UNIT 2 TOTAL REWRITE l
INITIALS
! 6.6.6 CC Pumps and Valves:
" PULLOUT". 2
- b. Place 2B52-28B,2P-11B breaker in " TEST". I1 ;
( c. Close 2P-1 IB breaker and leave control switch in " AUTO". 2
6.6.7 SW Pumps and Valves: '
- a. Operate P-32A, B & F 3
- b. Verify breaker "OPEN" with control switch in " AUTO" for P-32C, D & E. 3 l
l c. Shut 2SW-2907 and verify 2SW-2908 is shut. 3 NOTE: Pumpback ofrefueling cavity must be complete. 1 l l 6.6.8 Align 2P-10B for LHSI. ;
i i
- a. Place 2P-10B control switch to " PULLOUT". 2 l
- b. Shut 2RH-704B,2P-10B loop suction manual. 8 :
I c. Shut 2RH-706B,2P-10B high flow test line isol. 8 i
- d. Verify shut 2SI-852B. 4
- e. Open 2SI-856B. 4
- f. Verify 2RH-625 is open. 2,4
. g. Place 2P-10B control switch to " AUTO". 2 r -
l l
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NUCLEAR POWER BUSINESS UNIT ORT 3
! OPERATIONS REFUELING TESTS MAJOR IPTE ,
SAFETY INJECTION ACTUATION WITH LOSS OF Revision 28 9 7,,.; ENGINEERED SAFEGUARDS AC January 25,1997 UNIT 2 TOTAL REWRITE l
INITIALS i 6.6.9 Align 2P-10A for refueling cavity pumpback:
- a. Place 2P-10A control switch to " PULLOUT". 17
- b. Open 2RH-704A,2P-10A loop suction manual. 8
- c. Open 2RH-706A,2P-10A high flow test line isol. 8
- d. Verify shut 2SI-852A. 17
- e. Shut 2RH-701. 17
- f. Open 2SI-856A. 17
Lock 2RH-742B handwheel in position. 8,17
- h. Stop 2P-10A and place control switch to " PULLOUT". 17
- i. Shut 2SI-856A. 17
- j. Open 2RH-701. 17
- k. Review Step 6.1.7 responsibilities except substitute 2P-10A for 2P-10B. 8,17 6.6.10 Align 2P-14B:
- a. Position 2SI-862J, spray system high flow test line FCV, to the position recorded in Step 5.13.22. 16
- b. Open 2SI-862H. 16
- c. Verify open 2SI-870B. 4
, d. Verify shut 2SI-871B. 4
- e. Place 2P-14B control switch to " AUTO". -
4 Page 73 of 145 CONTINUOUS USE l
i l NUCLEAR POWER BUSINESS UNIT ORT 3
! OPERATIONS REFUELING TESTS MAJOR IPTE !
SAFETY INJECTION ACTUATION WITH LOSS OF Revision 28 l 6M ENGINEERED SAFEGUARDS AC January 25,1997 I UNIT 2 TOTAL REWRITE I INITIALS l
6.6.11 Align 2P-15B for HHSI:
- a. Verify open 2SI-825B 4
- b. Verify open 2SI-896B 4 i
- c. Verify shut 2SI-866B 4
- d. Place 2P-15B control switch to " AUTO". 4 I e. Shut 2SI-878B&D. 4 l 6.6.12 Verify Unit 2 CIV panels A&B indicate all Unit 2 CIVs open. 4 NOTE: Expect " UNIT 2 SAFEGUARDSMCCSUPPLY 6
- BREAKER TRIP" alarm (CO2F-4-7) when 2BS2-31B is closed.
NOTE: Breakers 2BS2-26C, 30B, 31A, 31B, and 40C must be 11 operatedlocally, as required.
- CAUTION
- THE CONTROL SWITCH MUST BE IN j
" PULLOUT" FOR ALL BREAKER i REPOSITIONING IE., TEST, RACK-IN, RACK-OUT.
t 6.6.13 Position the following 2B04 breakers l
1 2B52-26C 2B02 bus tie Test & Closed 6,11 l 2B52-28A 2P-2C Test & Closed 11 2B52-28B 2P-11B Test & Closed 2 2B52-28C B-21 Rack In & Closed 4 2B52-29B 2T-1D Test & Closed 2 .
2B52-29C K-3B Rack In & Closed 10 2B52-30B Z-14 Test & Closed 11 l 2B52-30C 2T-1E Test & Closed 2 l 2B52-31 A 2B-49 Rack In & Closed 11 l 2B52-31B 2B-42 Alt. Test & Closed 11
, 2B52-32C 2B-42 Rack In & Closed 4 2B52-40C 2B03 bus tie Test & Closed
- 6,11
- Control power fuses ir, stalled l
j Page 74 of145 CONTINUOUS USE
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! NUCLEAR POWER BUSINESS UNIT ORT 3 l
OPERATIONS REFUELING TESTS MAJOR IPTE SAFETY INJECTION ACTUATION WITH LOSS OF Revision 28 g, ENGINEERED SAFEGUARDS AC January 25,1997 UNIT 2 TOTAL REWRITE INITIALS i t
l 6.6.14 Remove the 4VI fuse in 2B00-25L of 2B04. I1 l
l 6.6.15 At cubicle 2A00-91 of 2A06, defeat UV follower relay l 2-27-lX1/A06 by opening test switch "G" on test switch l
I assembly 2-TS-27-3/A06. 12 l
1 6.6.16 Check 480 and 4160 V UV alarms cleared on C02. 6 6.6.17 Start 2W-ICI and IDI VNCC fans. 4 l.
l Page 75 of145 CONTINUOUS USE l .
NUCLEAR POWER BUSINESS UNIT ORT 3 ;
OPERATIONS REFUELING TSSTS MAJOR IPTE SAFETY INJECTION ACTUATION WITH LOSS OF Revision 28 ENGINEERED SAFEGUARDS AC January 25,1997 UNIT 2 TOTAL REWRITE :
INITIALS -
6.7 Loss of AC Followed by Automatic Safety Iniection (Train B) 6.7.1 Open the following valves: '
2SI-860C 4 2SI-860D 4 2SI-866B 4 6.7.2 Commence a countdown over the Gai-tronics to start the test and the CSR recorder. 1,15 NOTE: Steps 6.7.3 and 6.7.5 require close coordination 4,6 between the electrical breaker operator and the operator unblocking St.
NOTE: In Step 6. 7.4, test station 12 is to determine at what 12 point in the countdown the G03 & G04 starting air motors receive the start signal. Ifit isfrom the UVcircuit, it will occur between T(0) -4 seconds and T(0). Ifit isfrom the SI signal, it willoccurfrom T(0) to ~T(0) +2 seconds.
NOTE: The SIsequence time delay values listed are nominal 1,2,3,4 setpoint values. The actualtime delay values are deterraria.:dfrom the CSR recor :.<. s.
6.7.3 At time T(0)-4 seconds, de-energize bus 2A% by opening 2A52-49, normal supriy breaker. 6 6.7.4 Record countdown time at which G03 and G04 starting air motors receive a start signal. G03 12 G04 12 6.7.5 At time T(0), initiate a Train B auto SI signal by unblocking SI using Train B UNBLOCK switch only. 4 l
1 l
Page 76 of145 CONTINUOUS USE
._. = . . - _ _. .
NUCLEAR POWER BUSINESS UNIT ORT 3 I OPERATIONS REFUELING TESTS MAJOR l
IPTE SAFETY INJECTION ACTUATION WITH LOSS OF Revision 28
[j g ENGINEERED SAFEGUARDS AC January 25,1997 UNIT 2 TOTAL REWRITE INITIALS 6.7.6 At time T(0), observe:
1
- a. 2P-15B start 4
I i
6.7.8 At time T(0) +10 seconds, observe:
- a. P-38B start. Time _ 3
)
6.7.9 At time T(0) +15 and 20 seconds, observe the sequential stan l of P-32C and P-32D SW pumps respectively. 3 6.7.10 At time T(0) +25 seconds:
- a. Observe P-32E SW pump start, and 3
- b. Simultaneously start 2P-14B spray pump. 4 I
6.7.11 At time T(0) +40-50 seconds, observe restart of 2W-1C1 and l 1Dl, respectively. 4 6.7.12 At time T(0) +90 seconds:
- a. Stop the CSR recorder. 15
- b. Start 2P-10B for refueling cavity pumpback, if required. 1,17 1
l l
t Page 77 of 145 CONTINUOUS USE
l NUCLEAR POWER BUSINESS UNIT ORT 3 l OPERATIONS REFUELING TESTS MAJOR IPTE -
SAFETY INJECTlu ACTUATION WITH LOSS OF Revision 28 '
p.,gt ENGINEERED SAFEGUARDS AC January 25,1997 ;
UNIT 2 TOTAL REWRITE ,
INITIALS 6.7.13 Check the status of the following: :
l NOTE: The checks in this step may beperformed 1 concurrently or out ofthe sequence listed.
l a. Train B SI signal has aligned the appropriate Train B relays -
listed in ICP 10.22A. 15
- b. Reactor trip breakers:
2-52/RTA open 2 2-52/RTB open 2
- c. Following Safeguards MOVs open:
2SI-852B, B Train core deluge 4 2SI-878B, SI to Loop B cold leg 4 2SW-2908, SW return from VNCC 3
- d. Component Cooling AOVs shut:
2CC-LW63, Radwaste system CC supply 2 2CC-LW64, Radwaste system CC return 2
- e. Main feed punips and valves:
2P-28A, main feed pt mp, breaker open 2 2P-28B, main feed pump, breaker open 2 2CS-466, MFRV, shut 2 2CS-476, MFRV, shut 2 2CS-480, MFRV bypass, shut 2' 2CS-481, MFRV bypass, shut 2 l-l Page 78 of145 CONTINUOUS USE
NUCLEAR POWER BUSINESS UNIT ORT 3 OPERATIONS REFUELING TESTS MAJOR IPTE SAFETY INJECTION ACTUATION WITH LOSS OF Revision 28 d:T ENGINEERED SAFEGUARDS AC January 25,1997 UNIT 2 TOTAL REWRITE INITIALS
- f. 480 volt equipment and lockout relays:
2-86/B03 lockout not tripped 4
'2-86/B04 lockout tripped 4 2B52-28B, 2P-11B breaker open 2 2B52-31B, 2B-42 Alt. remains closed 11 2B52-31 A, 2B-49 breaker remains closed 11 2B52-32C, 2B-42 breaker remains closed 4 2B52-25B, 2X-14 breaker remains closed 6
- g. Control Room HVAC at C-67:
VNCSR-4850, CSR outside air damper shut 4 VNCR-4849C, Computer Room outside air damper shut ,4 W-14A tripped on UV with white light lit above control switch 4 W-14A UV white light lit on breaker 2B52-4211M. 8 1 I
- h. Battery charger supply contactors- l 2B42-491 open 4 i 2B42-4212B open l 4
- i. EDGs and breakers:
- 1. G01 does not start 5
- 2. G02 does not start 6 j
- 3. G03 starts 5
- 4. G04 starts 6
- 5. 2A52-96,2A06 normal supply breaker, open 6 1
- 6. 2A52-93, G04 to 2A06 supply breaker, closed 6
- 7. Record G04 KW load. KW 6 L
i Page 79 of 145 CONTINUOUS USE s .
NUCLEAR POWER BUSINESS UNIT ORT 3 OPERATIONS REFUELING TESTS MAJOR IPTE SAFETY INJECTION ACTUATION WITH LOSS OF Revision 28 gg ENGINEERED SAFEGUARDS AC January 25,1997 UNIT 2 TOTAL REWRITE
~
INITIALS t
- j. Receipt of alarms / warning lights:
NOTE: Alarmin 1 below and warninglightin 2 below willinitiallyfunction, but should clear as SWpumps are sequenced on.
- 1. " UNIT 2 CONTAINMENT RECIRC COOLERS WATER FLOW LOW" alarm on C01. (C-2-9) 4
- 2. Contaimnent vent cooler low water flow warning light on C01 benchboard section is illuminated for all coolers with SW flow <1020 gpm. 3
- 3. " UNIT 2 CONTAINMENT VENTILATION ISOLATION" alarm on C01. (C-2-8) 4
- 4. " UNIT 2 CONTAINMENT ISOLATION" alarm on ,
C01. (C-2-7) 4 :
- 5. "70% LEVEL /SI LOCKOUT" waming light '
illuminated on 2C03 for-Feedwater Loop A 2 {
Feedwater Loop B 2
- 6. " UNIT 2 4.16 KV BUS UNDERVOLTAGE" alarm on C02 (F-1-4). 6
- 7. " UNIT 2 480 V UNDERVOLTAGE" alarm on C02 (F-2-7) 6
- k. W-86, PAB Battery Room vent fan, shifts to slow speed.
(W-85 standby fan may operate until low flow alarm clears.) 13
2017B, supply SOV shuts (unlatched) 9 2017D, exhaust SOV shuts (unlatched) 9 i
l Page 80 of145 CONTINUOUS USE
NUCLEAR POWER BUSINESS UNIT ORT 3 OPERATIONS REFUELING TESTS MAJOR IPTE SAFETY INJECTION ACTUATION WITH LOSS OF Revision 28 ENGINEERED SAFEGUARDS AC January 25,1997 UNIT 2 TOTAL REWRITE INITIALS
2018B, supply SOV shuts (unlatched) 9 2018D, exhaust SOV opens (unlatched) 9-
- n. Radwaste steam AOVs:
SA-10, RS supply trip valve shut 9 SA-1, RS PCV shut (must look at local VPI and not the controller). 9
- o. Accumulator discharge MOV open contactor status:
2B52-424F,2SI-841B energized. 7 I
l 1
Page 81 of145 CONTINUOUS USE
NUCLEAR POWER BUSINESS UNIT ORT 3 OPERATIONS REFUELING TESTS MAJOR IPTE SAFETY INJECTION ACTUATION WITH LOSS OF Revision 28 p.g y ENGINEERED SAFEGUARDS AC January: 5,1997 UNIT 2 TOTAL REWRITE e
INITIALS
- p. CIVs on Isolatio , Panels A and B:
Position 2RM-3200B Shut 4 2SC-966C Shut 4 21A-3048 Shut 4 2RM-3200C Open 4 2RM-3200A Shut 4 2MS-2083 . Shut 4 2MS-2084 Shut 4 2SC-955 Open 4 21A-3047 Shut 4 2CV-313A Shut 4 2CV-371A Shut 4 2WG-1787 Shut 4 1 l
2CC-769 Shut 4 2CV-313 Open 4 2CV-371 Open 4 2MS-5959 Shut 4 2MS-5958 Shut 4 l 2WG-1786 Open 4 2VNPSE-3245 Shut 4 2VNPSE-3213 Shut 4 2WL-1728 Shut 4 2SC-966A Shut 4 2SC-966B Shut 4 2VNPSE-3244 Open 4 I 2VNPSE-3212 Open 4 2WL-1723 Open 4 2SC-951 Open 4 2SC-953 Open 4 Page 82 of 145 CONTINUOUS USE
NUCLEAR POWER BUSINESS UNIT ORT 3 OPERATIONS REFUELING TESTS MAJOR IPTE SAFETY INJECTION ACTUATION WITH LOSS OF Revision 28
, ENGINEERED SAFEGUARDS AC January 25,1997 '
UNIT 2 TOTAL REWRITE INITIALS I
Position ,
2RC-508 Shut 4 2RC-539 Shut 4 2WG-1789 Shut 4 2SI-846 Shut 4 2WL-1721 Shut 4 i i
2CV-1296 Open 4 2RC-538 Open 4 2WG-1788 Open 4 l 2WL-1698 Open 4 2WL-1003A Open 4 l 2WL-1003B Open 4
- q. Check Unit 14160 volt bus fast transfer inhibited with the ;
following control circuit continuity checks:
- 1. For the control circuit of 1 A52-37, l A03 to I A01 bus tie, measure:
(a) 0 Vdc to ground at TB6C-9 of 2C-167. 1 Record voltage. Vdc 15 (b) ~ -67 Vdc to ground at TB6C-10 of 2C-167.
Record voltage. Vdc 15
- 2. For the control circuit of 1 A52-55, I A04 to I A02 bus tie, measure:
(a) 0 V 'c to ground at TB6D-1 of 2C-167.
Record voltage. Vdc 15 (b) ~ -67 Vdc to ground at TB6D-2 of 2C-167. ,
Record voltage. Vdc l'5 Page 83 of 145 CONTINUOUS USE
NUCLEAR POWER BUSINESS UNIT ORT 3 OPERATIONS REFUELING TESTS MAJOR IPTE SAFETY INJECTION ACTUATION WITH LOSS OF Revision 28 g,' ENGINEEPED SAFEGUARDS AC January 25,1997 UNIT 2 TOTAL REWRITE INITIALS
- r. Check condensate pump trip circuit is not inhibited with the following CPA circuit continuity check:
- 1. Remove safeguards test lamp No. 861 " Containment Pressure Containment Isolation" in 2C-167. 15
- 2. Connect positive lead of VOM to test point TP-23 and the negative lead to terminal 10 of terminal strip PW in 2C-167. 15
- 3. Record ~ -67 VDC. VDC 15 NOTE: Do not install test lamp until required by procedure. 15
- s. Check that 2B52-405M, MCC 2B-40 Bus Isolation Bkr. to Non-Safety Loads is open, then reclose 2B52-405M. 12
- t. Check Unit 2 B Train SI short time delay circuit is functional to I A06:
- 1. At the door of 1 A00-82 on l A06, remove the undervoltage test panel cover. 12
- 2. Measure and record ~ +67 VDC from TP-6 to !
TP-G. Vdc 12 6.7.14 At time T(0) +7 minutes (or greater): i NOTE: Seven minutes allows two minutesfor load I sequencing, andjive minutes offullload operation.
- b. Reset (but da not Block) Train B St. 4 i
Page 84 of145 CONTINUOUS USE 9
NUCLEAR POWER BUSINESS UNIT ORT 3 l OPERATIONS REFUELING TESTS MAJOR l
IPTE SAFETY INJECTION ACTUATION WITH LOSS OF Revision 28 l # "6 ENGINEERED SAFEGUARDS AC January 25,1997 UNIT 2 TOTAL REWRITE INITIALS
- c. Record Train B LHSI flow per 2FI-928. apm 2
\
concurrently. i
- f. Reset 2-86/B04 lockout relay. 4
- g. Observe " UNIT 2 SAFEGUARDS RESET BYPASS ACTIVATED" light for Train B is illuminated (rear of ,
C01). 4 :
i i
- i. Observe Control Room vent system remains in Mode 2 (recirculation). 4 l
l'
- j. Reset W-14B UV lockout by depressing the black pushbutton on the door of cubicle 2B52-4211M, then
- 1. Observe white light go out at the cubicle door and 7
- 2. At the W-14B control switch on C-67. 4
- 3. Restart W-14B and observe W-14B remains operating. 4
- 4. This completes W-14B UV lockout testing. Stop W-14B and return W-14 selector switch to AUTO mode of operation. Select W-14A or W-14B control switch for " AUTO" operation with the remaining W-14 fan selected as a backup fan. 4 l
l
- k. Reset the "SI/UV" status light on C22, PAB Battery Room l ventilation panel, and observe W-86 fan shifnb fast speed.13 '
Page 85 of 145 CONTINUOUS USE
NUCLEAR POWER BUSINESS UNIT ORT 3 OPERATIONS REFUELING TESTS MAJOR :
IPTE SAFETY INJECTION ACTUATION WITH LOSS OF Revision 28 !
,. ENGINEERED SAFEGUARDS AC January 25,1997 UNIT 2 TOTAL REWRITE INITIALS
- 1. Locally open 2B52-31B,2B-42 alternate breaker, then rack out the breaker. 1I
- m. Check Unit 2 B Train SI short time delay signal is not functional to 1 A06:
- 2. Reinstall UV test panel cover. 12
- o. Check condensate pump trip circuit is inhibited with the
{
following CPA circuit continuity check:
the negative lead to terminal 10 of terminal strip PW in 2C-167. 15 l
- 2. Record ~ 0 VDC. VDC 15
- 4. Install test lamp in 2C-167 cabinet socket No. 861,
" Containment Pressure Containment Isolation". Installer 15 l
l l
l I
Page 86 of145 CONTINUOUS USE l' .
NUCLEAR POWER BUSINESS UNIT ORT 3 '
OPERATIONS REFUELING TESTS MAJOR I
IPTE SAFETY INJECTION ACTUATION WITH LOSS OF Revision 28 ;
ENGINEERED SAFEGUARDS AC January 25,1997 UNIT 2 TOTAL REWRITE i INITIALS I I
6.8 Test of G04 Automatic Load Sheddina and Restoration NOTE: Steps 6.8.1 through 6.8.5 may beperformed concurrently 1 andin any order.
NOTE: Breakers 2BS2-26C, 30B, and 40C must be 11 operatedlocally, as required.
- CAUTION
- THE CONTROL SWITCH MUST BE IN 2,4,6,11
" PULLOUT" FOR ALL BREAKER REPOSITIONING IE., TEST, RACK-IN, RACK-OUT.
6.8.1 Position the following 2B04 breakers:
2B52-26C 2B02 bus tie Test & Closed 6,11 2B52-28A 2P-2C Test & Closed 11 2B52-28B 2P-1IB Test & Closed 2 2B52-28C B-21 Rack In & Closed 4 ,
2B52-29B 2T-1D Test & Closed 2 l 2B52-29C K-3B Rack In & Closed 10 2B52-30B Z-14 Test & Closed 11 l 2B52-30C 2T-1E Test & Closed 2 2B52-40C 2B03 bus tie Test & Closed
- 6,11
- Insert control power fuses.
6.8.2 Verify 480 and 4160 V UV elanns on CO2 cleared.
(F-1-4 & F-2-7) 6 6.8.3 2B04 lockout relay:
- a. Remove power to lockout relay by opening MOB-208 in C01. 14
- b. Check receipt of" UNIT 2 COMMON CRITICAL .
CONTROL POWER FAILURE" alarm on CO2 (F-4-1) 6
- c. Verify white power available light for 2-86/B04 on rear of C01 is de-energized. 4 1
Page 87 of 145 CONTINUOUS USE 8 j
NUCLEAR POWER BUSINESS UNIT ORT 3 OPERATIONS REFUELING TESTS MAJOR IPTE SAFETY INJECTION ACTUATION WITH LOSS OF Revision 28 pv ENGINEERED SAFEGUARDS AC January 25,1997 UNIT 2 TOTAL REWRITE INITIALS 6.8.4 At 2A00-91 of 2A06:
{
- a. Restore UV follower relay 2-27-lX1/A06 by closing test switch "G" on test switch assembly 2-TS-273/A06. 12
)
- b. Defeat UV follower relay 2-27-2X1/A06 by opening test switch "E" on test switch assembly 2-TS-273/A06. 12 1
- c. Defeat degraded grid voltage follower relay 2-62-1X1/A06 ,
by opening test switch "A" on test switch assembly i 2-TS-62X/A06. 12 6.8.5 Closure of 2A52-96 breaker: )
- a. Place the control switch for 2A52-49 to the " PULLOUT" position. 6
- b. Inside breaker cubicle 2A52-49 of 2A04, identify TB2-9 ;
(wire #56) and TB2-10 (wire #55). TB2 is secor,d TB from the bottom. Check 11 Concur 1i
- c. Inside breaker cubicle 2A52-49 of 2A04, install ajumper between TB2-9 (wire #56) and TB2-10 (wire #55). TB2 is ,
second TB from the bottom. I1 '
- d. When the abovejumper is installed, then with the sync.
switch on, close 2A52-96. 6 6.8.6 Stop 2P-15B, then place control switch to " AUTO" and verify 2P-15B does not auto start. 4,17 NOTE: Countdown to start Cait recorder required. 1,15 6.8.7 When >15 minutes have elapsed from the time recorded in Step 6.7.8, then place the control switch for 2A52-93, G04 to 2A06 breaker to " PULLOUT". 6 Page 88 of 145 CONTINUOUS USE
l l NUCLEAR POWER BUSINESS UNIT ORT 3 l OPERATIONS REFUELING TESTS MAJOR l IPTE SAFETY INJECTION ACTUATION WITH LOSS OF Revision 28 g'g ENGINEERED SAFEGUARDS AC January 25,1997 UNIT 2 - TOTAL REWRITE l INITIALS
6.8.8 Observe
l l a. 2A52-96,2A04/2A06 bus tie, open. 6
- b. Auto closure of 2P-15B breaker. 4
- c. P-38B trip. 3 l d. Stop CSR recorder atter P-38B trip or 30 seconds after recorder start. 15
- f. Following breakers not trinned:
2B52-25B 2X-14 6 2B52-28B 2P-llB 2 2B52-31 A 2B-49 11 2B52-32C 2B-42 4
- g. Following breakers trinned:
2B52-405M 2B-40 12 2B52-26A 2W-lCl 4 2B52-26B 2W-IDI 4 2B52-26C 2B02 bus tie 6 2B52-27A 2P-14B 3 2B52-27B P-32D 3 2B52-27C P-32E 4 2B52-28A 2P-2C 2,11 2B52-28C B-21 4 2B52-29A 2P-10B 2,17 2B52-29B 2T-1D -2 l 2B52-29C K-3B 10 l- 2B52-30B Z-14 11
! 2B52-30C 2T-1 E 2 2B52-3iC P-38B . 3 l 2B52-40C 2B03 bus tie 6 Page 89 of145 CONTINUOUS USE
NUCLEAR POWER BUSINESS UNIT ORT 3 OPERATIONS REFUELING TESTS MAJOR '
IPTE <
SAFETY INJECTION ACTUATION WITH LOSS OF Revision 28 :
IC ENGINEERED SAFEGUARDS AC January 25,1997 UNIT 2 TOTAL REWRITE INITIALS 6.8.9 Green flag 2P-14B control switch. 4 6.8.10 Position 2RH-625 to full open. 2 NOTE: Recorder may be secured after auto reclosure of2W-1C1 15 and1D1 breakers.
6.8.11 Start CSR recorder on countdown for next step. 1.15 6.8.12 Place 2A52-93 control switch to " AUTO" and observe breaker closure. 5 6.8.13 Approximately 25 seconds after 2A52-93 closure, restart 2P-14B spray pump simultaneous with P-32E start. 4 6.8.14 Observe the sequential restart of-.
2P-15B, SI pump 4,17 2P-10B, RHR pump 2,17 P-38B, AF pump 3 ;
P-32D&E, SW pump Time 3 2W-l Cl, VNCC fan 4 2W-IDI, VNCC fan 4 ;
i 6.8.15 Throttle 2HC-625 for a flow of 200-300 gpm per 2F1-928. 2,17 l NOTE: Steps 6.8.16 and 6.8.17 may be perfornred concurrently. 1 6.8.16 Test of degraded grid voltage circuit on short time delay (SI signal present):
- a. Reclose 2A52-96. 6 NOTE: Expect an ~S second time delayfor breaker trip. 12
- b. Simultaneously depress and hold depressed the trip test pus!) buttons for relays 2-274/A06 and 2-275/A06 until breaker 2A52-96 trips, then release test buttons. 12
- c. Observe 2A52-96 breaker open. 6 Page 90 of145 CONTINUOUS USE G
NUCLEAR POWER BUSINESS UNIT- ORT 3 OPERATIONS REFUELING TESTS MAJOR IPTE SAFETY INJECTION ACTUATION WITH LOSS OF Revision 28 x ,, ENGINEERED SAFEGUARDS AC January 25,1997 1
UNIT 2 TOTAL REWRITE INITIALS ,
- e. Reclose 2A52-96. 6 1 I
- f. Simultaneously depress and hold depressed the trip test pushbuttons for relays 2-274/A06 and 2-276/A06 until ]
l breaker 2A52-96 trips, then release test buttons. 12
- g. Observe 2A52-96 breaker open. 6
)
- h. Reclose 2A52-96. 6
- i. At 2A00-91 of 2A06:
- 1. Restore UV follower relay 2-27-2X1/A06 by closing test switch "E" on test switch assembly 1 2-TS-273/A06. 12
- 2. Restore degraded grid voltage follower relay j 2-62-lX1/A06 by closing test switch "A" on test ,
switch assembly 2-TS-62X/A06. 12
- 3. Defeat degraded grid voltage follower relay !
2-62-2X1/A06 by opening test switch "B" on test switch assembly 2-TS-62X/A06. 12
- j. Simultaneously depress and hold depressed the trip test pushbuttons for relays 2-275/A06 and 2-276/A06 until !
breaker 2A52-96 trips, then release test buttons. 12
- k. Observe 2A52-96 breaker open. 6
- 1. Check receipt of" UNIT 2 4.16 KV BUS UNDERVOLTAGE" alarm on C02 (F-1-4) 6
- m. Reclose 2A52-96 6 4 .
Page 91 of145 CONTINUOUS USE
NUCLEAR POWER BUSINESS UNIT ORT 3 OPERATIONS REFUELING TESTS MAJOR IPTE SAFETY INJECTION ACTUATION WITH LOSS OF Revision 28
?% ENGINEERED SAFEGUARDS AC January 25,1997 UNIT 2 TOTAL REWRITE INITIALS t
- n. Simultaneously depress and hold depressed the trip test pushbuttons for relays 2-274/A06 and 2-275/A06 until breaker 2A52-96 trips, then release test buttons. 12
- o. Observe 2A52-96 breaker open. 6
- a. Observe six SW pumps in operation. 3
, service (SW-2930A or B), then open SW-2930A&B.
SW-2930 3
- c. Stop P-32A, B and F SW pumps. Leave control switches
, in " AUTO". 3
- d. Observe the following valves shut:
2SW-2880, Unit 2 turbine hall supply MOV 3 SW-2817, water treatment supply MOV 3 SW-2930B, spent fuel pool cooling MOV 3 SW-LW62, SW from blowdown evaporator 7
- e. Observe the following valves remain open: '
SW-2816, Service Building cooling MOV 3 SW-2930A, spent fuel pool cooling MOV 3 SW-LW61, SW to blowdown evaporator 7
- f. Restart p_n_e SW pump. 3 Page 92 of145 CONTINUOUS USE e
NUCLEAR POWER BUSINESS UNIT ORT 3 OPERATIONS REFUELING TESTS MAJOR l IPTE SAFETY INJECTION ACTUATION WITH LOSS OF Revision 28 l
., ,4 ENGINEERED SAFEGUARDS AC January 25,1997 !
UNIT 2 TOTAL REWRITE I INITIALS I
- g. Reopen valves:
SW-2817 7 l SW-LW62 7 2SW-2880 3
)
SW-2930B 3
as recorded in Step 6.8.17.b. 3 !
l
- i. Restart remaining SW pumps. 3 6.8.18 When Steps 6.8.16 and 6.8.17 are complete, then reset (but do not Block) Train B SI. 4 NOTE: Steps 6.8.19 and 6.8.20 may beperformed concurrently. l .
I 6.8.19 Test of degraded grid voltage circuit on long time delay (no SI !
signal):
NOTE: Expect an ~45 second time delayfor breaker trip. 12 \
- a. Simultaneously depress and hold depressed the trip test push buttons for relays 2-274/A06 and 2-275/A06 until breaker 2A52-96 trips, then release test buttons. 12 l
- c. Observe 2A52-96 breaker open. 6
- d. Close 2A52-96. 6
- e. Simultaneously depress and hold depressed the trip test buttons for relays 2-274/A06 and 2-276/A06 until breaker 2A52-96 trips, thtn release test buttons. 12 I
- f. Observe 2A52-96 breaker open. 6 Page 93 of145 CONTINUOUS USE
i NUCLEAR POWER BUSINESS UNIT ORT 3 l OPERATIONS REFUELING TESTS MAJOR l
IPTE SAFETY INJECTION ACTUATION WITH LOSS OF Revision 28
., ENGINEERED SAFEGUARDS AC January 25,1997 -
UNIT 2 TOTAL REWRITE I
INITIALS
- g. Restore degraded grid voltage follower relay 2-62-2X1/A06 by closing test switch "B" on test switch assembly 2-TS-62X' iO6. 12
- h. Defeat degraded grid voltage follower relay 2-62-IX1/A06 by opening test switch "A" on test switch assembly 2-TS-62X/A06. 12
- i. Reclose 2A52-96. 6
- j. Simultaneously depress and hold depressed the trip test pushbuttons for relays 2-275/A06 and 2-276/A06 until breaker 2A52-96 trips, then release test buttons. 12 *
- k. Observe 2A52-96 breaker open. 6
- 1. Reclose 2A52-96. 6
- m. Simultaneously depress and hold depressed the trip test pushbuttons for relays 2-274/A06 and 2-275/A06 until breaker 2A52-96 trips, then release test buttons. 12
- n. Observe 2A52-96 breaker open. 6
- o. Reset UV relay targets for 2-271,272,273,274,275, and 276/A06, as required. 12
- p. Restore degraded grid voltage follower relay 2-62-lX1/A06 by closing test switch "A" on test switch assembly 2-TS-62X/A06. 12 6.8.20 Close the following contactors from 2C-20:
2B42-491, D08 contactor. 4 NOTE: The 2C20, ASIP operator and a MTN 4,13 electrician at the contactorpanelmust communicate to accomplish thefollowing steps.
NOTE: To close contactor 2B42-4212B, 4,13 hold the contactor control switch on 2C20 in "CLOSE" while the electrician closes the
- contactor manually. ,
2B42-4212B, D109 contactor. 4,13 Page 94 of 145 CONTINUOUS USE
NUCLEAR POWER BUSINESS UNIT ORT 3 OPERATIONS REFUELING TESTS MAJOR IPTE SAFETY INJECTION ACTUATION WITH LOSS OF Revision 28 i . r ENGINEERED SAFEGUARDS AC January 25,1997 UNIT 2 - TOTAL REWRITE INITIALS 6.8.21 Restore 2A52-49 for operation:
- a. Place 2A52-49 control switch to " PULLOUT". 6
- b. Remove thejumper installed in Step 6.8.5.b between TB2-9 and TB2-10 in breaker cubicle 2A52 49. I1 _
- c. Place 2A52-49 control switch from " PULLOUT to the
" AUTO" position. Do not close 2A52-49 at this time. 6
, 6.8.22 Simulate Unit 1 Train B Si and observe action:
- a. In 2C20 (ASIP), identify slider at TB30-8. Check 14 Concur 4
- b. Open slider TB30-8. 14
- c. Observe contactors 2B42-491 and 2B42-4212B trip open. 4
- d. Reclose slider TB30-8. 14
- e. Verify slider TB30-8 closed. 4 !
6.8.23 Reclose 2B52-405M on MCC 2B40. 12 4
6.8.24 When >l5 minutes have elapsed since the time recorded in Step 6.8.14, then stop 2P-15B and place control switch to
" PULLOUT". 4,17 6.8.25 Stop the following G04 loads and place the control switch to 4
" PULLOUT":
2P-10B 2,17 2P-14B 4 6.8.26 Transfer 2A06 load from G04 to 2A04 per Attachment E. 6 d
Page 95 of145 CONTINUOUS USE
NUCLEAR POWER BUSINESS UNIT ORT 3 OPERATIONS REFUELING TESTS MAJOR IPTE SAFETY INJECTION ACTUATION WITH LOSS OF Revision 28
. , f,y ENGINEERED SAFEGUARDS AC January 25.1997 a UNIT 2 TOTAL REWRITE INITIALS NOTE: The remaining steps ofSection 6.8 may beperformed concurrently. 1 6.8.27 Adjust 2RH-742B as required to reduce flow and preclude stopping 2P-10A. 1,8,17 6.8.28 Open 2RH-625. 2,4 -
i 6.8.29 At 2800-25L of 2B04:
l
- a. Install the 4V1 fuse. 11 l
- b. Remove the 5VI fuse. I1 i
NOTE: Breakers 2B52-26C, 30B, and 40C must be operated locally, as required. 11
- CAUTION
- THE CONTROL SWITCH MUST BE IN 2,4,6,11
" PULLOUT" FOR ALL BREAKER l
REPOSITIONING IE., TEST, RACK-IN, RACK-OUT.
6.8.30 Position the following 2B04 breakers:
l 2B52-26C 2B02 bus tie Test & Closed 6,11 l 2B52-28A 2P-2C Test & Closed 1I 2B52-28B 2P-1IB Test & Closed 2 2B52-28C B-21 Rack In & Closed 4- l 2B52-29B 2T-1D Test & Closed 2 2B52-29C K-3B Rack In & Closed 10 2B52-30B Z-14 Test & Closed 11 2B52-30C 2T-1E Test & Closed 2 2B52-40C 2B03 bus tie Test & Closed
- 6,11
' Insert control power fuses. ]
4 Page 96 of145 CONTINUOUS USE
!. NUCLEAR POWER BUSINESS UNIT ORT 3 OPERATIONS REFUELING TESTS MAJOR IPTE
, SAFETY INJECTION ACTUATION WITH LOSS OF Revision 28
/* A 5 ENGINEERED SAFEGUARDS AC January 25,1997 UNIT 2 TOTAL REWRITE INITIALS :
6.9 Test of Unit 2 B Train Loss of AC with SI and G03 I
6.9.1 Enter a 7-day LCO for the unavailability of a standby emergency power source to 1 A06. DSS l
NOTE: Should Unit i experience a loss ofoffsitepower and/or 1,5 an SIactuation, then restore G03 to 1A06 by (in order) placing 2A52-87 controlswitch to " PULLOUT" and 1A52-80 controlswitch to " AUTO".
6.9.2 Place I A52-80, G03 to I A06, breaker control switch to
" PULLOUT". 5 6.9.3 Alignment of G03 to 2A06
- a. On CO2, place the G04 normal output breaker control switch "2A52-93, G04 DIESEL GENERATOR TO BUS 2A06 BREAKER," to " PULLOUT". 6
- b. Locally at C82, place the G04 normal output breaker control switch "2A52-93, G04 TO 2A06," to
" PULLOUT". 12 1
- CAUTION
- ENSURE THAT THE CONTROL 5,6 SWITCHES FOR BREAKERS 2A52-87 (G03) AND 2A57 3 (G04) ARE NOT PLACED IN "/.dTO" AT THE SAME TIME.
- c. On CO2, unlock (key 43) and place the G03 attemate output breaker control switch "2A52-87, G03 DIESEL GENERATOR TO BUS 2A06 BREAKER," to " AUTO". 5 6.9.4 Place 2P-15B control switch to " AUTO" and verify 2P-!5B does not auto start. Place 2P-14B control switch to " AUTO". 4 NOTE: Step 6.9.6 must be initiated before G0315 minute 1 cooldown timer expires or an unnecessaryfast restart will
, occur.
6.9.5 Commence a shutdown of G03 per Attachment F. 5
, . Page 97 of 145 CONTINUOUS USE
NUCLEAR POWER BUSINESS UNIT ' ORT 3 !
OPERATIONS REFUELING TESTS MAJOR IPTE a SAFETY INJECTION ACTUATION WITH LOSS OF Revision 28 7 ENGINEERED SAFEGUARDS AC January 25,1997 UNIT 2 TOTAL REWRITE INITIALS NOTE: Countdown requiredto start CSR recorder. Recorder 1,15 may be stopped 90 seconds after Step 6.9.6.
NOTE: Manual restart of 2P-14B required coincident wille auto 4 j restart ofP-32E. I 6.9.6 Initiate a 2A06 and 2B04 loss of AC and SI reinitiation by placing the control switch for 2A52-96,2A04 to 2A06 bus tie, to " PULLOUT". -6 j
6.9.7 Observe
- a. P-38B, P-32D&E trip. 3 l
- b. 2W-lCl and IDI trip. 4
- c. 2P-15B breaker close on a dead bus. 4,17 i
- d. G03 return to speed and voltage. 5 i
- e. 2A52-87 close. 5 h
6.9.8 Observe or perform G03 load sequencing in following order:
- a. 2P-10B starts 2,17
- b. P-38B restarts 3
- c. P-32D restans 3 j
- d. P-32E restarts, then simultaneously restart 2P-14B. 3,4
- e. 2W-ICI restarts 4
- f. 2W-IDI restarts Time 4 !
- g. Record G03 KW load KW 5 6.9.9 When >90 seconds after the restoration of power to 2A06 and i 2B04, then reset (but do not block) Train B SI. 4 Page 98 of 145 CONTINUOUS USE
NUCLEAR POWER BUSINESS UNIT ORT 3 OPERATIONS REFUELING TESTS MAJOR IPTE '
SAFETY INJECTION ACTUATION WITH LOSS OF Revision 28 ,
ENGINEERED SAFEGUARDS AC January 25,1997 UNIT 2 TOTAL REWRITE INITihLS 6.9.10 Observe:
- a. Following breakers not trinned:
2B52-25B 2X-14 6 2B52-28B 2P-llB 2 2B-49 2B52-31 A 11
~
- b. Following breakers trinned:
2B52-26C 2B02 bus tie 6 2B52-28A 2P-2C 2,11 2B52-28C B-21 4 2B52-29B 2T-1 D 2 -
2B52-29C K-3B 10 2B52-30B Z-14 11 2B52-30C 2T-lE 2 2B52-40C 2B03 bus tie 6 NOTE: Countdown to start CSR recorder required. 1,15 NOTE: 2P-MB control switch must be greenflagged before 4 manually closing breaker.
6.9.11 When >l5 minutes from the time recorded in Step 6.9.8, then place 2A52-87, G03 to 2A06, breaker control switch to
" PULLOUT", and four seconds later retum the control switch to " AUTO" smartiv. 5 6.9.12 Observe / perform:
e 2P-15B breaker remains closed. 4 ,
l l b. 2P-10B restans 2 l l "
! c. P-38B restarts 3 Page 99 of145 CONTINUOUS USE
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' OPERATIONS REFUELING TESTS MAJOR IPTE SAFETY INJECTION ACTUATION WITH LOSS OF Revision 28 l
ENGINEERED SAFEGUARDS AC . January 25,1907 UNIT 2 TOTAL REWRITE ,
INITIALS I
- d. P-32D restarts 3 i
- e. P-32E restarts, then simultaneously restart 2P-14B 3,4
- f. 2W-lC1 and 2W-IDI restart Time 4 6.9.13 Throttle 2HC-625 for a flow of 200-300 gpm per 2F1-928. 2,17 NOTE: During the next step, hold at each holdpointfor I& C 1,15 i to check MG-6 relay latching clearance.
6.9.14 When >90 seconds after the re: ; oration ofpower to 2A06 and 2B04:
- b. Reset Train B SI (I&C hold point). 4 NOTE: Perform Steps 6.9.14.c, d and e, if Train B 1,15 SIA-A and/or SIA-B latch clearance was adjusted i in Step 6.9.14.a. Otherwise NA Steps 6.9.14.c, d and e.
- c. Unblock Train B SI. 4
- e. Reset Train B SI. 4 NOTE: Perform Step 6.9.14.fifFB-1 andfor 1,15 1 FB-2 latch clearance was adjusted in Step '
6.9.14.b. Otherwise NA Step 6.9.14.f.
l
- f. Reset 2CS-481, feedwater bypass AOV. 2 I g. Verify 2B52-405M on MCC 2B40 is tripped, then reset (close) 2352-405M. 12
- h. At 2B00-25L of 2B04, install the 5VI fuse. . I1 Page 100 of145 CONTINUOUS USE
I NUCLEAR POWER BUSINESS UNIT ORT 3 ;
OPERATIONS REFUELING TESTS MAJOR !
IPTE SAFETY INJECTION ACTUATION WITH LOSS OF Revision 28
- %. ENGINEERED SAFEGUARDS AC January 25,1997 !
UNIT 2 TOTAL REWRITE i INITIALS 6.9.15 Stop the following G03 loads by placing the control switch to " PULLOUT":
2P-15B 4,17 2P-14B 4 2W-1C1 4 2W-1D1 4 6.9.16 Shut AF-4020 and leave AF-4020 control switch in the manual mode of operation. 3 6.9.17 Reset UV relay targets for UV relays 2-271,272,273,274, 275, and 276/A06 as required. 12 l
\
NOTE: Steps 6.9.21 through 6.9.27 may beperformed concurrently 1 with Steps 6.9.18 through 6.9.20.
6.9.18 Transfer 2A06 load from G03 to 2A04 per Attachment E. 5 6.9.19 When 2A52-87 breaker is open. then place I A52-80 breaker control switch to " AUTO" and exit standby emergency power supply 7-day LCO to I A06. 5, DSS i 6.9.20 Aligmnent of G04 or G03 to 2A06:
1
- a. The operational readiness of G04 as required by Technical
{
Specifications 15.4.6.A.1 and TS 84 is l SAT, UNSAT,(circle one) 1 I
- b. The operational test of P-207B, fuel oil transfer pump, as required by Technical Specification 15.4.6.A.5 and TS 84 is SAT, UNSAT (circle one) 1 i Page 101 of145 CONTINUOUS USE
NUCLEAR POWER BUSINESS UNIT ORT 3 OPERATIONS REFUELING TESTS MAJOR IPTE SAFETY INJECTION ACTUATION WITH LOSS OF Revision 28 l 4- -
ENGINEERED SAFEGUARDS AC January 25,1997 UNIT 2 TOTAL REWRITE INITIALS
- c. The response and performance of G04 to sequenced loading under conditions ofloss of off-site safeguards AC coincident with SI in accordance with Technical Specification 15.4.6.A.2 and Section 6.7 of this test is SAT., UNSAT (circle one) I
- d. The response and performance of G04 to total automatic load shedding and restoration of vital loads in accordance with Technical Specification 15.4.6.A.2 and Section 6.8 of this test is SAT., UNSAT (circle one). I
- e. If all four of the G04 tests specified in Steps 6.9.20.a through 6.9.20.d are satisfactory, then proceed with Step 6.9.20.f and NA Step 6.9.20.g. Otherwise proceed to align G03 per Step 6.9.20.g and NA Step 6.9.20.f. I
- f. Align G04 to 2A06:
. On CO2, place the G03 alternate output breaker control switch, "2A52-87, G03 DIESEL GENERATOR TO BUS 2A06 BREAKER", to
" PULLOUT" and enable mechanical key lock. 5
- CAUTION
ARE NOT PLACED IN
" AUTO" AT THE SAME TIME.
. On CO2, place the G04 normal output breaker control switch "2A52-93, G04 DIESEL GENERATOR TO BUS 2A06 BREAKER", to " AUTO". 6 Page 102 of145 CONTINUOUS USE 1
NUCLEAR POWER BUSINESS UNIT ORT 3
! OPERATIONS REFUELING TESTS MAJOR IPTE SAFETY INJECTION ACTUATION WITH LOSS OF Revision 28 l g...y. ENGINEERED SAFEGUARDS AC January 25,1997 l l UNIT 2 TOTAL REWRITE l INITIALS e Locally at C81, verify the G03 alternate output i breaker control switch, "2A52-87, G03 DIESEL GENERATOR TO BUS 2A06 BREAKER",is in
" PULLOUT" and the mechanical key lock is enabled.
12
- Locally at C82, place the G04 normal output breaker control switch "2A52-93, G04 DIESEL GENERATOR TO BUS 2A06 BREAKER", to
" AUTO". 12
- g. To complete G03 to 2A06 alignment, then at C81, unlock (key 43) and place the G03 alternate output breaker control l switch, "2A52-87, G03 DIESEL GENERATOR TO BUS 2A06 BREAKER", to " AUTO". 12
- h. Exit 24-hour LCO for P-32D&E DSS
- i. Exit 7-day LCO for P-38B. DSS
- j. Exit 7-day LCO to 2A06. DSS 6.9.21 2-86/B04 lockout relay:
- a. Restore power to 2-86/B04 by closing MOB-208 in C01. 14 l b. Check " UNIT 2 COMMON CRITICAL CONTROL POWER FAILURE" are on C02 cleared. (F-4-1) 6
- c. Verify white power available light for 2-86/B04 on rear of C01 is de-energized. 4
! 6.9.22 Reset Train B:
l C1 4 i
CVI 2 6.9.23 Reset K-2B UV Lockout, then test run/ operate K-2B as required. , 4 Page 103 of145 CONTINUOUS USE l .
NUCLEAR POWER BUSWESS UNIT ORT 3 OPERATIONS REFUELING TESTS MAJOR l IPTE SAFETY INJECTION ACTUATION WITH LOSS OF Revision 28 f- ENGINEERED SAFEGUARDS AC January 25,1997 UNIT 2 TOTAL REWRITE l INITIALS 6.9.24 With the control switch in " PULLOUT", place the following I
breakers in the " TEST" condition:
2A52-88 2P-15B 4,12 2B52-27A 2P-14B 4,11 6.9.25 Shut or verify shut the following HHSI valves:
2SI-866A 4 ,
2SI-866B 4,17 2SI-878B 4 2SI-878D 4 6.9.26 Shut the following containment spray system valves:
2SI-860C -
4 2SI-860D 4 2SI-862H 16 6.9.27 When >l5 minutes have elapsed since the time recorded in Step 6.9.12, then
- a. When 2P-10B is powered from offsite AC, then stop 2P-10B and place control switch to " PULLOUT". 2
- b. Shut 2SI-856B. 4
- c. Shut 2SI-852B. 4 NOTE: Steps 6.9.28 and 6.9.29 may beperformed concurrently 1 wille testSections 6.10 and 6.11.
6.9.28 Continue pumping the refueling cavity to the RWST with 2P-10A as determined by DSS, then stop 2P-10B and place control switch to " PULLOUT". .
17 Page 104 of145 CONTINUOUS USE
NUCLEAR POWER BUSINESS UNIT ORT 3 OPERATIONS REFUELING TESTS MAJOR IPTE SAFETY INJECTION ACTUATION WITH LOSS OF Revision 28 g,, ENGINEERED SAFEGUARDS AC January 25,1997 UNIT 2 TOTAL REWRITE INITIALS 6.9.29 Post -test recovery of Train .B Containment Spray System
- a. Flush the seal area of 2P-14B by spraying the seal area with warm DI water. 16
- b. Red lock shut 2SI-862H,2P-14B high flow test line isolation.
Red Lock No. 16
- c. Attach a vent hose from 2SI-869B to a local exhaust duct, then open 2SI-869B and depressurize the discharge header to atmospheric pressure. 16
Red Lock No. 16
- e. With DSS concurrence, open and red lock 2SI-868B, containment spray header isolation. Otherwise NA this step.
Red Lock No. DSS,16
- f. Open and red lock 2SI-874B, Train B eductor suction.
Red Lock No. 16 Page 105 of 145 CONTINUOUS USE
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SAFETY INJECTION ACTUATION WITH LOSS OF Revision 28
! ENGINEERED SAFEGUARDS AC January 25,1997 l UNIT 2 TOTAL REWRITE INITIALS l 6.10 Test of Train B Manual SI. Non-Safecuards Load StrintJ ,. and SW i E_umn Seauencine 6.10.1 Close reactor trip breakers 2-RTA and 2-RTB. 2 NOTE: Steps 6.10.2 through 6.10.6 may beperformed concurrently 1 andin any order.
6.10.2 Position the following breaker control switches to " AUTO":
2P-14B 4 2P-15B 4 l 2W-1C1 4 ,
2W-1D1 4 l NOTE: Breakers 2B52-33C, 39C and 40C must be 11 \
operatedlocally, as required. '
NOTE: 2B04 breaker condition, ie., "RA CKED-IN" or 2,4,6,11 l
" TEST" has been previously established. '
6.10.3 Close or verify closed the following 2B04 breakers:
2B52-26C 2B02/B04 bus tie Test & Closed 6,11 2B52-28A 2P-2C Test & Closed 11 2B52-28B 2P-11B Test & Closed 2 2B52-28C B-21 Rack In & Closed 4 2B52-29B 2T-1D Test & Closed 2 2B52-29C K-3B Rack In & Closed 10 2B52-30B Z-14 Rack In & Closed 11 l 2B52-30C 2T-1E Test & Closed 2 l 2B52-40C 2B03/B04 bus tie Test & Closed
- 6,11
- Insert control power fuses.
Page 106 of145 CONTINUOUS USE
! NUCLEAR POWER BUSINESS UNIT ORT 3 l OPERATIONS REFUELING TESTS MAJOR IPTE l SAFETY INJECTION ACTUATION WITH LOSS OF Revision 28 l na ENGINEERED SAFEGUARDS AC January 25,1997 UNIT 2 TOTAL REWRITE INITIALS t
! 6.10.4 Isolate Train A manual SI signal generation from both manual SI push-buttons by opening slider UMN-2 on riser 25 in C01. 14 1 Verified 4 l
j 6.10.5 Reposition main feed regulator valves:
l
- a. Clear at least 3 of 4 low TAVG signals. 15
- b. Open 2CS-466 and 476. 2 6.10.6 When 15 miautes have elapsed since the time recorded in Step 6.9.12.f, then operate P-32A, B and F, stop P-32C, D
! and E, and leave all SW pump control switches in " AUTO". 3 l
NOTE: Step 6.10.8 must be initiated before G03 and G04 1,5,6 15 minute cooldown timers expire or an unnecessaryfast restart willoccur.
! 6.10.7 Commence a shutdown of G03 and G04 per Attachment F:
- a. G03 5
- b. G04 6 l
NOTE: Countdown required to start CSR recorder. Recorders 1,11 may be stopped 90 seconds after Step 6.10.8.
6.10.8 With G03 and G04 on their cooldown timers, initiate a manual l
SI using the left-hand pushbutton. 4 l
/
l 1
Page 107 of 145 CONTINUOUS USE
l NUCLEAR POWER BUSINESS UNIT ORT 3 l OPERATIONS REFUELING TESTS MAJOR l
IPTE l
SAFETY INJECTION ACTUATION WITH LOSS OF Revision 28 l u, ENGINEERED SAFEGUARDS AC January 25,1997 UNIT 2 l TOTAL REWRITE i INITIALS l 6.10.9 Observe: i
- RTA breaker open 2 l RTB breaker open 2
" MANUAL S!" reactor trip alarm on 2C04 2 I 2CS-466 shut 2 2CS-476 shut 2 P-38B trip, then sequence restart Time 3 P-32C sequenced start 3 !
4 P-32D sequenced start 3 l l
P-32E sequenced start 3 i 2P-15B breaker closed 4 2W-1Cl breaker sequenced closed 4 l 2W-1D1 breaker sequenced closed 4 ;
2-86/B04 lockout tripped 4 2-86/B03 lockout not tripped 4 G03 return to speed and voltage 5 G01 unaffected 5 G04 return to speed and voltage 6 G02 unaffected 6 l l SIM-B tripped 15
{
SIM-A not tripped 15 )
l 6.10.10 Following 2B04 breakers not trinned:
2B52-25B 2X-14 6 2B52-28A 2P-2C 2 2B52-28B 2P-llB 2 2B52-31 A 2B-49 11 l 2B52-32C 2B-42 4 l Page 108 of 145 CONTINUOUS USE i.
l NUCLEAR POWER BUSINESS UNIT ORT 3 OPERATIONS REFUELING TESTS MAJOR IPTE SAFETY INJECTION ACTUATION WITH LOSS OF Revision 28 l /'.:'s ENGINEERED SAFEGUARDS AC January 25,1997 :
UNIT 2 TOTAL REWRITE INITIALS 6.10.11 Following 2B04 breakers tripped:
2B52-26C 2B02 bus tie 6 2B52-28C B-21 4 2B52-29B 2T-lD 2 2B52-29C K-3B 11 2B5:.-30B Z-14 11 2B52-30C 2T-1 E 2 2B52-40C 2B03 bus tie 6 6.10.12 Close 2P-14B breaker and observe breaker remains closed. 4 '
6.10.13 Perform SIM-B latch clearance checks and adjustment. 15 6.10.14 When at least 90 seconds have elapsed since initiation of manual SI, then reset Tmin B SI. (I&C hold) 4 6.10.15 Clear the " MANUAL SI" reactor trip alarm on 2C04. 2 __
6.10.16 When >15 minutes have elapsed since the time recorded in Step 6.10.9, then initiate a manual SI using the right-hand pushbutton. 4 l
6.10.17 Observe:
j
" MANUAL SI" reactor trip alarm on 2C04 2 P-38B trip, then sequence restart 3 SIM-B tripped (I&C hold) 15 SIM-A not tripped 15 l
i l .
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OPERATIONS REFUELING TESTS MAJOR IPTE SAFETY INJECTION ACTUATION WITH LOSS OF Revision 28 i g ENGINEERED SAFEGUARDS AC January 25,1997 UNIT 2 TOTAL REWRITE ;
INITIALS I l
6.10.18 When at least 90 seconds have elapsed since initiation of ;
manual SI, then-I
- b. Reset 2-86/B04 lockout relay 4
- c. Stop P-38B. 3 !
- d. Open 2P-14B breaker and place control switch to l
" PULLOUT". 4 {
- e. Open 2P-15B breaker and place control switch to
" PULLOUT". 4 i
- f. Open 2W-1C1 and IDI breakers and place control switches !
to " PULLOUT". 4
- h. Open 2P-11B breaker and place control switch to
" PULLOUT". 2 6.10.19 Train B Test Recovery ;
i NOTE: The remaining sub-steps may be 1 performed concurrently in any order. In the interim, continue with test section 6.11.
i
- a. G03 and G04 are not involved in the remainder of the test and are to be load tested or secured per Attachment J. 5,6
- b. Close slider UMN-2 in C01 restoring Train A manual SI capability. 14 Verified 4
- c. Measure ~ - 67 VDC to ground on each side of slider UMN-2 thus verifying Train A manual Si circuit .
continuity. 14 Page 110 of 145 CONTINUOUS USE
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UNIT 2 TOTAL REWRITE INITIALS
- e. Close 2B52-28C, B-21 supply 4
- CAUTION
- TIIE CONTROL SWITCII 2,4,5,11 MUST BE IN " PULLOUT" FOR ALL BREAKER REPOSITIONING, IE.,
TEST, RACK-IN, RACK-OUT.
- f. Reposition the following 2B04 breakers: ;
Breaker Number Breaker Condition 2B52-26C 2B02 bus tie RACKED-OUT 6,11 2B52-27A 2P-14B RACKED-OUT 4,11 2B52-28A 2P-2C RACKED-OUT 2,11 2B52-28B 2P-11B RACKED-IN 2,11 ,
2B52-29B 2T-ID RACKED-OUT 2,11 2B52-30C 2T-1E RACKED-OUT 2,11 !
2B52-40C 2B03/B04 bus tie RACKED-OUT* 6,11 !
- 2803/B04 bus tie fuses removed 11 i
- g. Control Room HVAC:
- 1. Shift CR ventilation system to normal mode (Mode 1). 4
- 2. Check VNCSR-4850 and VNCR-4849C have auto l re-opened. 4
- 3. Check " CONTROL ROOM VENTILATION RECIRC MODE" alarm on C01 cleared. (B-4-9) 4
- h. Open SA-10, then verify that SA-1 auto reopens. Must observe local SA-1 VPI versus controller output. 9 1
(
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- j. W-85/86 fan alignment:
- 1. Reset the "SI/UV" status light on C22, PAB Battery Room ventilation panel, and observe W-86 fan shift to fast speed. 8
- 2. Operate W-86 in slow speed. 8 1
4
- 1. Verify operability of K-3B, then operate K-3B as required.10 l
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INITIALS 6.11 Verification of Manual Containment Isolation and Individual Train Actuation:
6.11.1 Reset both trains:
CVI 2 CI 4 6.11.2 Initiate a manual containment isolation using the left-hand pushbutton. 4 6.11.3 Observe that the following relays trip:
Cl-A A Train CI 15 CI-B B Train CI 15 V-A A Train CVI 15 V-B B Train CVI 15 i 6.11.4 Observe " UNIT 2 CONTAINMENT ISOLATION" and
" UNIT 2 CONTAINMENT VENTILATION ISOLATION" alarms present on C01. (C-2-7 and C-2-8) 4 6.11.5 Reset:
C1 4 CVI 2 6.11.6 Initiate a manual containment isolation using the right-hand pushbutton. 4 6.11.7 Observe that the following relays trip:
CI-A A Train CI 15 CI-B B Train CI 15 V-A A Train CVI 15 V-B B Train CVI -
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,, ENGINEERED SAFEGUARDS AC January 25,1997 UNIT 2 TOTAL REWRITE INITIAI.S 6.11.8 Observe " UNIT 2 CONTAINMENT ISOLATION" and
" UNIT 2 CONTAINMENT VENTILATION ISOLATION" alarms present on C01. (C-2-7 and C-2-8) 4 6.11.9 Reset:
CI 4 CVI 2 i 6.11.10 Open the following valves, then place the respective control ;
switch to " AUTO":
- 2CC-LW-64 2 6.11.11 Shift Control Room ventilation system to normal mode (Mode 1). 4 6.11.12 Restore IA to containment. 4 6.11.13 Open other CI and CVI valves as required. DSS 6.11.14 Recovery of RCDT Pumps and Drain Line
- c. Remove danger tags from WL-1698A&B, then open WL-1698A. 7 I
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- UNIT 2 TOTAL REWRITE i INITIALS
- e. Adjust 2WL-1726 and 1727 to their respective throttled position. 7
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/J." ENGINEERED SAFEGUARDS AC January 25,1997 UNIT 2 TOTAL REWRITE INITIALS l 7.0 RECOVERY FROM THE TEST l
NOTE: The order ofthe steps in the recoveryfrom the test is at the discretion ofthe DSS.
7.1 Verify Unit 2 4.16 KV safeguards buses powered from the normal source:
Position 2A52-76 2A03 to 2A05 Closed 2A52-49 2A04 to 2A06 Closed 2A52-96 2A04 to 2A06 Closed ,
2A52-75 2A05 to 2X13 Closed 2A52-89 2A06 to 2X14 Closed -
2A52-67 G02 to 2A05 Open 2A52-93 G04 to 2A06 Open ;
i 7.2 Verify 480 volt safeguards buses powered from the normal source:
Position 2B52-40B 2X13 to 2003 Closed 2B52-25B 2X14 to 2B04 Closed l
2B52-40C 2B03 to 2B04 Open 2B52-39C l
2B03 to 2B01 Open 2B52-26C 2B04 to 2B02 Open 2B52-38B 2B03 to 2B32 Closed 2B52-32C 2B04 to 2B42 Closed 7.3 Verify EDGs are aligned for normal standby operation:
l l G01 G02 G03 G04 l
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UNIT 2 TOTAL REWRITE INITIALS 7.4 The following steps are to be performed by the MTN/I&C group '
electricians with OPS group assistance / direction as required:
7.4.1 Disconnect the multipoint recorder (s) from the following test points:
I&C Initials l
2P-15A, SI pump breaker 2P-15B, SI pump breaker 2P-10A, RHR pump breaker 2P-108, RHR pump breaker l P-38A, AF pump breaker P-388, AF pump breaker i P-32A, SW pump breaker i P-32B, SW pump breaker ;
P-32C, SW pump breaker P-32D, SW pump breaker P-32E, SW pump breaker P-32F, SW pump breaker 2W-1 Al, VNCC fan breaker 2W-1B1, VNCC fan breaker 2W-lCl, VNCC fan breaker 2W-1Dl, VNCC fan breaker
~
G01 or G02 to 2A05 breaker
~
G03 or G04 to 2A06 breaker 2A05, voltage sensor j 2A06, voltage sensor 2C-157, A SI signal 2C-167, B SI signal 7.4.2 2SI-841 A&B, accumulator discharge MOVs:
- a. Verify breakers open:
NUCLEAR POWER BUSINESS UNIT ORT 3 OPERATIONS REFUELING TESTS MAJOR IPTE SAFETY INJECTION ACTUATION WITH LOSS OF Revision 28 ENGINEERED SAFEGUARDS AC January 25,1997 UNIT 2 TOTAL REWRITE INITIALS f
- 1. Identify cubicle 2B52-324F Check Concur -
- 2. Reconnect the motor leads at the common loadside terminals of the contactors. Connect T1-T1, T2-T2 and T3-T3. Torque to 20 inch-pounds.
MTN
- 3. Identify cubicle 2B52-424F. g Check Concur ,
- 4. Reconnect the motor leads at the common loadside :
terminals of the contactors. Connect TI-T1, T2-T2 and T3-T3. Torque to 20 inch-pounds. ,
- 5. Verify the motor leads at the common loadside terminals of 2B52-324F and 2B52-424F are properly connected. Verify
- c. Danger tag open and padlock breaker per OP-3C requirements:
- a. Verify 2P-28A&B breaker control switches in
" PULLOUT."
- b. Rack out:
l
- 1. 2A52-23,2P-28A breaker on 2A01 MTN
- 2. 2A52-30,2P-28B breaker on 2A02 .
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- c. In 2C03 at riser 50:
- 1. Remove jumper between TPAB-11 and TPAD-11.
(2P-28A) /
MTN
- 2. Removejumper between TPAD-1 and TPAD-2.
(2P-28A) /
MTN
- 3. Remove jumper between TPAJ-2 and TPAL-1. :
(2P-28B) /
MTN
- 4. Remove jumper between TPAK-3 and TPAK-4.
(2P-28B) /
MTN
- 5. Close slider TPAD-9. /
MTN
- 6. Close slider TPAK-11. /
MTN ;
7.4.4 Restore the D-09 and D-109 contactor interlocks in 2C-20.
- a. Close slider TBl1-8 for IB52-491. /
MTN
- b. Close slider TB27-4 for 2B52-391. /
MTN
- c. Close slider TB29-1 for IB52-3212H. /
MTN l
- d. Close slider TB9-11 for 2B52-4212B. /
MIN 7.5 Restore battery chargers and batteries to normal lineup in accordance with 0133. Verify the spare charger contactor supply breakers at both MCCs are closed.
s 7.6 RcMr.1 Unit I and Unit 2 SG blowdown /AF pump interlock defeat switch to the "OFF" position and return keys to the DSS key locker.
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7.7.1 Remove danger tag series and return the following equipment to service. ;
- a. Z-14, turbine building crane
- b. Z-29, turbine building elevator
- c. IZ-30, Ul facade elevator 7.7.2 Restore PAB and service building ventilation systems to normal.
7.7.3 Restore 2RE-211/212 and 2P-707A to service. ;
7.8 Letdown Gas Strinners 7.8.1 Position key-operated 43/ sal switch on C-180 to the
" NORMAL" position, then return the key to the DSS. !
7.8.2 If not previously performed, then perform the valve testing of
)
IT-605. Follow the directions ofIT-605 for the recovery of the i letdown gas strippers.
7.9 If no blowdown evaporator maintenance is planned, then return the I blowdown evaporator to service per OI 16 and the DSS.
7.10 Restoration of systems complete per ICP 10.22A.
l&C 7.11 If RMP 172 was performed, then DSS to complete RMP 172 Sections 8.0, Verification, and 9.0, Restoration.
I DSS I 7.12 Record all MTE identification numbers used during ORT 3 on CHAMPS i task sheet.
OPS MIN 1&C l
. ESE l
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ENGINEERED SAFEGUARDS AC January 25,1997 UNIT 2 TOTAL REWRITE ATTACHMENT A Test of Emereency DC Lichtine NOTE: This test should beperformed between 0.100 and 0700 hours0.0081 days <br />0.194 hours <br />0.00116 weeks <br />2.6635e-4 months <br /> to minimize work disruption andforpersonnelsafety.
When test signals are present in reactorprotection or safeguards logic systems and the signalgenerator(s) is(are) suppliedfrom lighting system power, then a reactor trip and/or emergency safeguardsfeature trip signal and alarm may be generated upon the interruption ofnormallighting power.
INITIALS 1.0 Announce over the Gai-tronics that there will be a test involving the loss of normal lighting lasting ~5 seconds affecting the U2 turbine hall, and the control room.
2.0 Test of emergency DC lighting: I 2.1 Open 2B52-46C on 2B-01, XL-05 feeder. l 2.2 Observe control room DC lighting energized.
)
2.3 Reclose 2B52-46C on 2B-01 to restore normal lighting.
2.4 Observe DC lighting secured.
3.0 Reset fire protection system alarms on D-408, D-412.
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7 , ENGINEEFED SAFEGUARDS AC January 25,1997 l UNIT 2 TOTAL REWRITE i
l ATTACHMENT B Date
! DSS 1.0 PRIMARY AUXILIARY BUILDING AREA 1.1 Valve Alienment POSITION INITIALS SW-LW61 SW to blowdown evaporator Air On & Nor. O SW-LW62 SW from blowdown evaporator Air On & Nor. O RS-2 SA-10 manual isolation. S RS-2A SA-10 steam trap root isolation S RS-SAIO Unit 2 radwaste steam supply trip valve Air On 1.2 Verifv breaker closed for the followine components:
2B-32 INITIALS 2B-42 INITIALS 1B-32 INITIALS 2SI-878D 2SI-878B SW-2816 2SI-852A 2SI-852B SW-2930A 2SW-2907 2SW-2880 W-85 SW-2817 1 B-42 2SW-2908 W-86 SW-2930B 1.3 C-22. PAB Battery Room Vent. Panel 1.3.1 Verify that "SI RESET" W-85 and "SI RESET" W-86 status lights are off.
1 1.3.2 Verify W-85 and W-86 speed select switches are set to " LOW."
l 1.3.3 Position the fan mode selector switches to operate W-85 fan in "RUN" and W-86 fan in " AUTO."
1.3.4 Verify SW for battery room cooling is properly aligned. .
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Attachment B )
INITIALS 1.4 Blowdown Evaporator Control Panel l
NOTE: Ifno indicationfor SA-9, checkfuses cubicle 4D ofB-46. If l no indicationfor SA-10, checkfuses cubicle 4FofB-46. \
Verify valve position indication is illuminated for the following: l l
RS-SA9 l
RS-SAIO SW-LW61 I SW-LW62 l 2.0 CONTROL ROOM. C01 1
2.1 Safeguards Component Alignment POSITION 2W-1A1 Containment accident fan control switch Auto /Off 2W-1B1 Containment accident fan control switch Auto /Off l 2W-lCl Containment accident fan control switch - Auto /Off I 2W-IDI Containment accident fan control switch Auto /Off !
2SI-871A Spray pump suction from RHR MOV S 2SI-871B Spray pump suction from RHR MOV S 2SI-841A l A accumulator discharge MOV S 2SI-841B B accumulator discharge MOV S l 2SI-852A Core deluge MOV Auto + S l 2SI-852B Core deluge MOV Auto + S 2SI-866A 2P-15A discharge MOV S 2SI-866B 2P-15B discharge MOV S 2'".V-2880 SW to Unit 2 turbine building MOV Auto + 0 SW-1816 SW to service building air conditioner MOV Auto + 0 SW-28i7 SW to water treatment MOV Auto + 0 SW-2930A SW to spent fuel pit cooling MOV Auto + 0 SW-2930B SW to spent fuel pit cooling MOV Auto + 0 2SW-2907 SW from containment coolers MOV Auto + S 2SW-2908 SW from containment coolers MOV Auto + S Remarks:
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- l. , ENGINEERED SAFEGUARDS AC January 25,1997 UNIT 2 TOTAL REWRITE l
ATTACHMENT C CONTAINMENTISOLATION VALVES Verify or perform the prerequisite, then open each of the listed CIVs.
Valve ID Function Prereouisite Initials 7 2VNPSE-3244 Purge supply Containment vented ,
2VNPSE-3245 Purge supply Containment vented 2VNPSE-3212 Furge exhaust Containment vented 2VNPSE-3213 Purge exhaust Containment vented 2CV-1296 Aux. charging line isolation None ;
2CV-371 Letdown isolation 2CV-427 shut i 2CV-371 A Letdown isolation 2CV-427 shut 2CV-313 RCP seal return 2CV-313B shut 2CV-313A RCP seal retum 2CV-313B shut !
2CC-769 CCW return from excess letdown HX None 2MS-5959 A SG blowdown 2MS-2042 shut 2MS-5958 B SG blowdown 2MS-2045 shut 1
2RM-3200A Containment air sample return None '
2RM-3200B Containment air sample supply None 2RM-3200C Containment air sample supply None 21A-3047 IA to containment N 2aligned to PORVs 2IA-3048 IA to containment N 2aligned to PORVs '
2WL-1723 Sump A drain Tape open 2WL-1728 Sump A drain None 2MS-2083 A SG sample Sample secured 2MS-2084 B SG sample Sample secured 2SI-846 Accumulators nitrogen supply HP nitrogen secured at source 2RC-508 Reactor makeup water to containment 2RC-508 shut 2SC-966A Pzr vapor saraple Sample sink valve shut -
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ENGINEERED SAFEGUARDS AC January 25,1997
)
UNIT 2 TOTAL REWRITE i Attachment C Valve ID Function Prereauisite Initials i 2SC-966B Pzr liquid sample Sample sink valve shut 2SC-966C Hot leg sample Sample sink valve shut 2RC-538 PRT gas sample 2RC-540 shut 2RC-539 PRT gas sample 2RC-540 shut
{
NOTE: Below listed valves controlledfrom tire PAB !
2WL-1003A RCDT pump suction Refer to RCDT lineup in i ORT 3 l
2WL-1003B RCDT pump suction Refer to RCDTlineup in ORT 3 2WL-1698 RCDT divert to -19' sump Refer to RCDTlineup in l ORT 3 l 2WL-1721 RCDT outlet Refer to RCDT lineup in ORT 3 2WG-1786 RCDT vent Vent header isolation 2WG-1716 and 2RC-527 shut if RCDT has oxygen atmosphere 2WG-1787 RCDT vent Vent header isolation 2WG-1716 and 2RC-527 shut if RCDT has oxygen atmosphere 2WG-1788 RCDT gas sample 2WG-1717 shut 2WG-1789 RCDT gas sample 2WG-1717 shut 2SC-951 Pa vapor sample Sample sink valve shut .
2SC-953 Pzr liquid sample Sample sink valve shut 2SC-955 Hot leg sample Sample sink valve shut Remarks:
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UNIT 2 TOTAL REWRITE l
ATTACHMENT D i G02(G0DPROCEDURE G02 / G01 1.0 Transfer bus 2A05 from the G02 (G01) diesel generator to its normal power .
source 2A03. l NOTE: Ensure start is recorded on PBF-2014, " Generator Start and Load ReliabilityInformation Sheet".
1.1 Turn the G02 (G01) mode selector switch to " Exercise." /
1.2 Depress the G02 (G01) fast govemor reset pushbutton momentarily. /
1.3 Adjust the G02 (G01) frequency to 60 Hz with the governor control switch. /
1.4 Adjust the G02 (G01) voltage to 4160 V with the voltage regulator control switch. /
NOTE: Beforeproceedingfurther, check G02 (G01) breaker closed and CO2 voltmeters indicate normal safeguards power available to 2A 05.
i
- CAUTION
- DO NOT ATTEMPT TO PLACE MORE THAN ONE SYNCHRONIZING SWITCH TO "ON" AT THE SAME TIME; EACH PARALLELING OPERATION MUST BE DONE INDEPENDENT OF OTHERS. '
1.5 Turn the synchronizing switch to "ON" for breaker 2A52-76. /
l 1.6 Observe the synchronizer voltmeters and synchroscope. / l l
1.6.1 Determine which voltmeter indicates diesel generator output and adjust sane to equal or slightly exceed (2 volts or less) that of the normal supply - through operation of the diesel generator
" VOLTAGE REGULATOR CONTROL SWITCH." /
l.6.2 Adjust the diesel generator frequency to obtain synchroscope p indication SLOW IN FAST" direction (2 to 5 RPM) through i
operation of the diesel generator " GOVERNOR CONTROL l SWITCH." /
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% 2. January 25,1997 UNIT 2 TOTAL REWRITE i Attachment D G02 / G01 1.7 When the synchroscope approaches 12 o' clock (10*/1.7 min before),
then close breaker 2A52-76. /
1.8 Operate the G02 (G01) voltage regulator control switch to adjust KVARs as required. /
l.9 Turn off the synchroscope. / ;
1.10 Operate the G02 (G01) governor control switch to reduce the load on G02 (G01) to 100 kW. /
l 1.11 Open G02 (G01) output breaker 2A52-67 (2A52-73). /
1 1.12 Operate the G02 (G01) voltage regulator control switch to adjust G02 J (G01) voltage to 4160 V. /
1.13 Place the G02 (G0l} mode selector switch to " AUTO." / j l
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f "- ENGINEERED SAFEGUARDS AC January 25,1997 UNIT 2 TOTAL REWRITE !
ATTACHMENT E G04 (G03) PROCEDURE G04 / G03 1.0 Transfer bus 2A06 from the G04 (G03) diesel generator to its normal power ,
source 2A04. !
. NOTE: Ensure start is recorded on PBF-20H, " Generator Start and Load ReliabilityInformation Sheet".
1.1 Ensure G03 (G04) output breaker 2A52-87 (2A52-93) is closed and that C-02 voltmeters indicate " NORMAL SAFEGUARDS POWER" is ;
available from 2A04. / i 1.2 Verify that the "2A06 TO 2A04 BUS TIE BREAKER" 2A52-96 is open. /
. 1.3 Verify that the "2A04 TO 2A06 BUS TIE BREAKER" 2A52-49 is closed. /
- CAUTION
- DO NOT ATTEMPT TO PLACE TWO BREAKER SYNCHRONIZING SWITCHES TO "ON" AT THE SAME TIME; EACH PARALLELING OPERATION MUST BE DONE INDEPENDENT OF OTHERS.
1.4 Turn the synchroraizing switch to "ON" for bus 2A06 normal supply 3 breaker (2A52-96). /
1 1.5 Observe the synchronizer voltmeters and synchroscope. ;
1.5.1 Determine which voltmeter indicates diesel generator output and adjust same to equal or slightly exceed (2 volts or less) that of the normal supply - through operation of the diesel generator
" VOLTAGE REGULATOR CONTROL SWITCH". /
1.5.2 Adjust the diesel generator frequency to obtain synchroscope indication " SLOW IN FAST" direction (2 to 5 RPM) through operation of the diesel generator " GOVERNOR CONTROL SWITCH". /
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1 ENGINEERED SAFEGUARDS AC January 25,1997 l
UNIT 2 TOTAL REWRITE l Attachment E G04 / G03
- CAUTION
- ENSURE THAT THE LOAD ON THE GENERATOR IS
>I00 KW, AFTER CLOSING THE NORMAL SUPPLY <
BREAKER TO PREVENT REVERSE POWER TRIP. I I
1.6 Close the nomial supply breaker 2A52-96 to bus 2A06 when the !
synchroscope isjust before 12:00, and within the green band !
(10'/1.7 min.). / 1 l
1.7 Adjust KVARs as necessary by operation of the " DIESEL GENERATOR I VOLTAGE REGULATOR" control switch. /
l.8 Turn the synchronizing switch for bus 2A06 normal supply breaker l 2A52-96 to "OFF." / :
1.9 Verify that B52-405M, the MCC B-40 bus isolation breaker, is closed. /
1.10 Reduce the load to approximately 100 kW by adjustment of the " DIESEL GENERATOR GOVERNOR" control switch. / l 1.11 Drive KVARs to zero with the " DIESEL GENERATOR VOLTAGE I REGULATOR" control switch. / !
l 1.12 "OPEN" the diesel generator G04 (G03) output breaker 2A52-93 I (2A52-87). /
1.13 Adjust the frequency and voltage to 60 Hz and 4160 volts respectively. /
1.14 Verify the " DIESEL GENERATOR MODE SELECTOR" switch on C02 is in " AUTO". /
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ATTACHMENT F 1.0 Commence a shutdown of emercency diesel G01 l
1.1 Check that G01 output breakers 2A52-73 and 1 A52-60 are open.
1.2 Turn the G01 mode selector switch to " EXERCISE."
1.3 Depress the G01 fast start governor reset pushbutton momentarily.
1.4 Operate the G01 governor control switch to adjust G01 frequency to 60 Hz. l 1.5 Operate the G01 voltage regulator control switch to adjust G01 voltage to 4160 V.
1.6 Turn the G01 control switch to "STOP."
1.7 Turn the G01 output breaker control switches to " TRIP," then back to
" AUTO."
l 1.8 Turn the G01 mode selector switch to " AUTO." )
2.0 Cc.mmence a shutdown of emereency diesel G03 2.1 Check the diesel generator output breakers 2A52-87 and 1 A52-80 are "OPEN."
2.2 Turn the "G03 DIESEL GENERATOR CONTROL" switch to " START" at panel C-02 then release.
2.3 Place the " DIESEL GENERATOR CONTROL" switch to "STOP" at panel C-02.
2.4 Note the green " READY-FOR-LOAD" light goes out.
, 2.5 Verify the " DIESEL GENERATOR MODE SELECTOR" switch at C-02
! is in " AUTO."
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, ENGINEERED SAFEGUARDS AC January 25,1997 l UNIT 2 TOTAL REWRITE I Attachment F i
INITIALS ;
3.0 Commence a shutdowm of emergency diesel G02 i
3.1 Check that G02 output breakers 2A52-67 is open.
3.2 Tum the G02 mode selector switch to " EXERCISE."
i 3.3 Depress the G02 fast start governor reset pushbutton momentarily. !
3.4 Operate the G02 governor control switch to adjust G02 frequency to 60 Hz.
3.5 Operate the G02 voltage regulator control switch to adjust G01 voltage to 4160 V.
3.6 Turn the G02 control switch to "STOP." ;
3.7 Turn the G02 output breaker control switches to " TRIP," then back to
" AUTO."
3.8 Turn the G02 mode selector switch to " AUTO."
i 4.0 Commence a shutdown of emercency diesel G04 t
4.1 Check the diesel generator output breakers 2A52-93 and 1 A52-86 are i "OPEN."
4.2 Turn the "G04 DIESEL GENERATOR CONTROL" switch to " START" at panel C-02 then release. '
4.3 Place the " DIESEL GENERATOR CONTROL" switch to "STOP" at l panel C-02. I 4.4 Note the green " READY-FOR-LOAD" light goes out.
~
i 4.5 Verify the " DIESEL GENERATOR MODE SELECTOR" switch at C-02 i is in " AUTO."
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NUCLEAR POWER BUSINESS UNIT ORT 3 OPERATIONS REFUELING TESTS MAJOR IPTE SAFETY INJECTION ACTUATION WITH LOSS OF Revision 28 l (L. ENGINEERED SAFEGUARDS AC UNIT 2 January 25,1997 l
l TOTAL REWRITE ATTACHMENT G ORT 3 ROSTER !
j STATION STATION OPERATOR OPERATOR
- NO. LOCATION QUALIFICATION NAME I Control Rm SRO l
(ReliefDSS)
, 2 2C03 & 2C04 CO '
- (Days CO) '
3 C01 Left CO !
(Relie0 4 C01 Right CO l (Relie0 5 CO2 G01 & G03 CO (Relie0 6 CO2 G02 & G04 CO/ DOS (Relie0 j 7 C59, Cl80 & AO '
2B42 PAB (Relie0 8 2B32 PAB AO 2P-10A&B (Relie0 9 SA-1 & 10 AO 2MS-2017 & 2018 (Relie0 !
10 IA/SA Comp. TH AO G01, G02, G03 & G04 (Relie0 11 Breakers - CSR Elec 12 2B391,2A05 & 2A06 Elec UV relays 13 2B42128 - PAB Elec C22 - PAB 14 Sliders - CR Elec 15 CR-CSR I&C (3)
Computer Rm Recorders - CSR l 16 2P-14 & 2P-15 AO j
pumproom (relieO i
17 C01,2C03 CO Page 132 of 145 CONTINUOUS USE 4
l l NUCLEAR POWER BUSINESS UNIT ORT 3 l OPERATIONS REFUELING TESTS MAJOR IPTE l SAFETY INJECTION ACTUATION WITH LOSS OF Revision 28 {
' / ENGINEERED SAFEGUARDS AC January 25,1997 l UNIT 2 TOTAL REWRITE I
l l ATTACHMENT H i
ORT 3 TAGOUT LISTING ~
LD Nomenclature Position l 2CV-313B Seal return man iso. Shut 2MS-2042 2HX-1 A blowdown isol. AOV control switch Shut 2MS-2045 {
2HX-1B blowdown isol. AOV control switch Shut l
2WL-1723 Sump A drain AOV control switch Open i 2MS-316 2HX-1 A sample manual isol. Shut l 2MS-317 2HX-1B sample manual isol. Shut 2SI-838A High pressure N2 supply to accumulator Shut 2SI-838B High pressure N2 supply to accumulator Shut 2RC-508A RMUW to containment manual isol. Shut 2SC-956A Pzr steam space sample mamtal isol. Shut 2SC-956B Pzr liquid space sample manualisol. Shut i 2SC-956C Hot leg sample manualisal. Shut l 2RC-540 PRT to GA sample manualisol. Shut 1WL-1698 U1 RCDT to sump AOV IA supply (FC) Shut l WL-1698A U1 and U2 RCDT drain manualisol. Shut !
WL-1698B Common RCDT drain line IVTC Shut l 2WL-1726 2P-18 discharge manual isol. Shut !
2WL-1727 2P-66 discharge manual isol. Shut 2WL-1698 U2 RCDT to sump AOV control switch at C-59 Open l 2RC-527 PRT to VH AOV control switch Shut 2WG-1716 RCDT to VH manualisol. Shut 2WG-1717 RCDT to GA sample manualisol. Shut P-20 P-20 control switch on C-59 Off BE-15 Waste evap. feed filter bypass Shut BE-115 Waste evap. feed filter outlet Shut D-08 AC supply breaker to D-08 on D08 door panel Open D-107 AC supply breaker to D-107 on D107 door panel Open i 2B52-391 D-09 A Train AC supply bkr. Open !
2B52-4212B D-109 B Train AC supply bkr. Open )'
1MS-251 IHX-1 A supply to RS manual isol. Shut 1MS-252 1HX-1B supply to RS manualisol. Shut
- RS-64 RS high pressure header vent Open 3 2SI-868A Spray header manual isol. Shut 2SI-868B Spray header manualisol. Shut 2SI-860A 2P-14A discharge MOV control switch S & Aut,o i 2SI-860B 2P-14A discharge MOV control switch S & Auto 2SI-860C 2P-14B discharge MOV control sw. S & Auto !
, Page 133 of145 CONTINUOUS USE
NUCLEAR POWER BUSINESS UNIT ORT 3 f OPERATIONS REFUELING TESTS MAJOR IPTE SAFETY INJECTION ACTUATION WITH LOSS OF Revision 28 ENGINEERED SAFEGUARDS AC January 25,1997 UNIT 2 TOTAL REWRITE Attachment H ID Nomenclature Position 2SI-860D 2P-14B discharge MOV control sw. S & Auto 2SI-874A 2P-14A eductor NAOH isol. Shut 2SI-874B 2P-14B eductor NAOH isol. Shut 2SI-866A 2P-15A discharge MOV bkr. & control switch Valve shut, bkr open 2SI-866B 2P-15B discharge MOV bkr. & control switch Valve shut, bkr open 2SI-862K Spray high flow test line isol. Shut Z-14 disconnect Turbine building crane disconnect Open PP9, Bkr 1 1Z-30, Unit 1 facade elevator Open B52-211DL Z-29, Turbine building elevator Open i
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e
NUCLEAR POWER BUSINESS UNIT ORT 3 OPERATIONS REFUELING TESTS MAJOR t IPTE :
SAFETY INJECTION ACTUATION WITH LOSS OF Revision 28 i /h ENGINEERED SAFEGUARDS AC January 25,1997 l UNIT 2 TOTAL REWRITE ;
l !
ATTACHMENTI 1.0 SECURING G01 OR G02 DIESEL AFTER ORT-3 TEST COMPLETED i (LOADING NOT REQUIRED).
NOTE: Ensure start is recorded on, " Gene. ator Start and Load Reliability ;
Information Sheet," PBF-2014. l NOTE: If G01/G02 unloaded run time exceedsfour hours, then mark Steps 1.1 through 1.16 as N/A andproceed to Section 2.0.
G01/ G02 1.1 Before proceeding further, check the diesel generator output breakers are "OPEN. /
1.2 Turn the " MODE SELECTOR" to " EXERCISE." /
1 1.3 Depress the fast start governor reset pushbutton " momentarily." /
i 1.4 Adju'st frequency to 60 Hz with " GOVERNOR CONTROL SWITCH." /
1.5 Adjust voltage to 4160 V with " VOLTAGE REGULATOR CONTROL SWITCH." /
1.6 Fill the diesel fuel oil sump tank to approximately 475 gallons by pushing the start button for the sump tank fuel oil pumps at the " engine control panel." /
1.7 When the level in the sump tank reaches 475 gallons, push the "STOP" button for the sump tank fuel oil pumps. /
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NUCLEAR POWER BUSINESS UNIT ORT 3 OPERATIONS REFUELING TESTS MAJOR IPTE SAFETY INJECTION ACTUATION WITH LOSS OF Revision 28 ,
, ENGINEERED SAFEGUARDS AC January 25,1997 '
UNIT 2 TOTAL REWRITE Attachment I G01/ G02 ;
- CAUTION
- ACCOMPLISH STEPS 1.8,1.9 AND 1.10 IN A TIMELY MANNER; THESE ENABLE THE DIESEL GENERATOR TO AUTOMATICALLY FAST START. I 1.8 Turn the " DIESEL GENERATOR CONTROL SWITCH" to "STOP."
The green ready-to-load light will go out when the diesel slows down and disagreement lights will show on both breaker control switches. /
1.9 Turn breaker control switches to trip and back to auto to reset both white lights. This resets output breaker lockout relays. /
1.10 Turn the " MODE SELECTOR" to " AUTO;" restoring the diesel to its standby status. /
1.11 Drain engine air boxes while at idle speed (one valve and pipe plug; volume normally <250 ml). /
1.12 The diesel will idle for about i1M minutes before stopping, at which time the amber diesel-started light will go out. /
1.13 Retum the service water pumps to the number required for existing plant conditions (2 minimum). /
NOTE: Ensure day tank levelis greater than 72%.
1.14 Verify diesel generator day tank fill has automatically taken place or manually operate the system if necessary. A 4-hour supply of fuel oil must be maintained for G01/G02. This corresponds to 72% level in the day tank and 400 gallons in the sump tank. /
1.15 Ensure P-206A and P-207A fuel oil pump control switches on C-01 are left in " AUTO" (neutral) position subsequent to refill. /
. 1.16 After engine has been secured for at least 3 minutes, verify fuel oil system No. I <2 psig and check SCR relay in C-64/C-65 dropped out (plunger down). /
l 1.17 Declare G01/G02 back in service and exit 7-day LCO. /
Page 136 of 145 CONTINUOUS USE
NUCLEAR POWER BUSINESS UNIT ORT 3 ;
OPERATIONS REFUELING TESTS MAJOR i IPTE !
SAFETY INJECTION ACTUATION WITH LOSS OF Revision 28 ENGINEERED SAFEGUARDS AC January 25,1997 UNIT 2 TOTAL REWRITE Attachment I i
G01/ G02
[
2.0 SECURING THE DIESEL GENERATOR AFTER ORT-3A TEST !
COMPLETED (DIESEL LOADING REQUIRED).
NOTE: Ensure start is recorded on, " Generator Start and Load Reliability Information Sheet," PBF-2014.
NOTE: Section 2.0 is only required if G0HG02 unloaded run time exceeded four hours during theperformance ofORT3.
2.1 Turn the " MODE SELECTOR" to " EXERCISE." /
2.2 Depress the fast start governor reset pushbutton " momentarily." /
2.3 Adjust frequency to 60 Hz with " GOVERNOR CONTROL SWITCH." /
2.4 Adjust voltage to 4160 V with " VOLTAGE REGULATOR CONTROL ;
SWITCH." / !
- CAUTION
- DO NOT ATTEMPT TO PLACE TWO BREAKER SYNCHRONIZING SWITCHES TO "ON" AT THE ;
SAME TIME; EACH PARALLELING OPERATION MUST BE DONE INDEPENDENT OF OTHERS.
2.5 Turn the synchronizing switch to "ON" for the desired A05 bus breaker: /
G01 to I A05 - Bkr 1 A52-60 G02 to 2A05 - Bkr 2A52-67 Page 137 of145 CONTINUOUS USE
. .~ . . . .- .
NUCLEAR POWER BUSINESS UNIT ORT 3 OPERATIONS REFUELING TESTS MAJOR IPTE SAFETY INJECTION ACTUATION WITH LOSS OF Revision 28 (W a ENGINEERED SAFEGUARDS AC January 25,1997 UNIT 2 TOTAL REWRITE Attachment I G01/ G02 2.6 Observe the synchronizer voltmeters and synchroscope. /
2.6.1 Determine which voltmeter indicates diesel generator output l and adjust same to equal or slightly exceed (2 volts or less) that of the normal supply - through operation of the diesel generator
" VOLTAGE REGULATOR CONTROL SWITCH." /
2.6.2 Adjust the diesel generator frequency to obtain synchroscope indication " SLOW IN FAST" direction (2 to 5 RPM) through ;
operation of the diesel generator " GOVERNOR CONTROL l SWITCH." /
NOTE: Insure dieselloading remains within rated capacity after breaker closure in next step.
NOTE: IfP-32A, B and Fare not in service, then they willsequence "0N" when the output breaker is closed.
2.7 Close the breaker to the desired A05 bus (as determined in 2.5 above),
when the synchroscope approaches 12:00, (10 /1.7 min. before). /
4 2.8 Adjust kvars in the out direction as necessary by operation of the diesel generator " VOLTAGE REGULATOR CONTROL SWITCH." /
o 2.9 Turn off the synchroscope (synchronizing switch selected in 2.5 above !
placed to "OFF").
/
2.10 "OPEN" ISW-2907,1SW-2908,2SW-2907 and 2SW-2908, containment vent cooler outlet valves, as necessary for service water header pressure
! control. / i 2.11 Begin one hour run at 2500-2700 kW and 500 KVARs. /
l 2.12 Reduce the load (kW) to the diesel generator by adjustment of the
" DIESEL GOVERNOR CONTROL SWITCH." /
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l NUCLEAR POWER BUSINESS UNIT ORT 3 l OPERATIONS REFUELING TESTS MAJOR IPTE SAFETY INJECTION ACTUATION WITH LOSS OF Revision 28 ENGINEERED SAFEGUARDS AC
- y,y, January 25,1997 UNIT 2 TOTAL REWRITE Attachment I G01/ G02 NOTE
- Leave breaker control switch in " auto" (neutral) position.
2.13 With diesel generator load at approximately 100 kW and zero kvars, open the diesel generator output breaker to desired bus:
G-01 0 G_02 1 A05 - Bkr 1 A52-60 2A05 - Bkr 2A52-67 2.14 Adjust diesel generator voltage to 4160 V with " VOLTAGE REGULATOR CONTROL SWITCH." /
2.15 Fill the diesel fuel oil sump tank to approximately 475 gallons by pushing the start button for the sump tank fuel oil pumps at the " engine control panel." /
2.16 When the level in the sump tank reaches 475 gallons, push the "STOP" button for the sump tank fuel oil pumps. /
- CAUTION
- ACCOMPLISH STEPS 2.17,2.18 AND 2.19 IN A TIMELY MANNER; THESE ENABLE TH'E DIESEL GENERATOR TO AUTOMATICALLY FAST START. l 2.17 Turn the " DIESEL GENERATOR CONTROL SWITCH" to "STOP." i' The green ready-to-load light will go out when the diesel slows down and disagreement light will show on both breaker control switches. /
2.18 Turn breaker control switches to trip and back to auto to reset both white lights. This resets output breaker lockout relays. /
2.19 Turn the " MODE SELECTOR" to " AUTO;" restoring the diesel to its standby status. /
l 2.20 The diesel will idle for about 11M minutes before stopping, at which time f the amber diesel-started light will go out. /
2.21 Drain engine air boxes while at idle speed (one valve and pipe plug; .
j volume normally s250 ml). /
I Page 139 of145 CONTINUOUS USE
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NUCLEAR POWER BUSINESS UNIT ORT 3 I OPERATIONS REFUELING TESTS MAJOR IPTE SAFETY INJECTION ACTUATION WITH LOSS OF Revision 28 MT ENGINEERED SAFEGUARDS AC January 25,1997 !
UNIT 2 TOTAL REWRITE I Attachment I G01/ G02 l 2.22 Return the service water pumps to the number required for existing plant conditions (2 minimum). /
NOTE: Ensure day tank levelis greater than 72%. i 2.23 Verify diesel generator day tank fill has automatically taken place or manually operate the system if necessary. A 4-hour supply of fuel oil must be maintained for G01/G02. This corresponds to 72% level in the !
day tank and 400 gallons in the sump tank. /
2.24 Ensure P-206A and P-207A fuel oil pump control switches on C-01 are left in " AUTO" (neutral) position subsequent to refill. /
2.25 After engine has been secured for at least 3 minutes, verify fuel oil system No. I <2 psig and check SCR relay in C-64/C-65 dropped out (plunger down). /
2.26 Declare G01/G02 back in service and exit 7-day LCO. /
i Page 140 of145 CONTINUOUS USE l
NUCLEAR POWER BUSINESS UNIT ORT 3 OPERATIONS REFUELING TESTS MAJOR l IPTE SAFETY INJECTION ACTUATION WITH LOSS OF Revision 28-l gy ENGINEERED SAFEGUARDS AC January 25,1997 UNIT 2 TOTAL REWRITE ATTACHMENTJ 1.0 SECURING G03 OR G04 DIESEL AFTER ORT-3 TEST COMPLETED (LOADING NOT REQUIRED).
NOTE: Ensure start is recorded on, " Generator Start and Load Reliability Information Sheet," PBF-2014.
NOTE: If G03/G04 unloaded run time exceedsfour hours, then mark Section 1.0 as N/A andproceed to Section 2.0.
G03 / G04 1 1
1 1.1 Before proceeding further, check the diesel generator output breakers '
"OPEN." /
1.2 Verify that the MCC B-40 Bus isolation Bkr. to Non-Safety Loads B52-405M is Closed for the appropriate diesel. /
1.3 Verify the " DIESEL GENERATOR MODE SELECTOR" switch at C-02 is in " AUTO." /
l 1.4 Turn the appropriate " DIESEL GENERATOR CONTROL" switch to l
" START" at panel C-02 then release. / l i
1.5 Place the appropriate " DIESEL GENERATOR CONTROL" switch to '
"STOP" at panel C-02. / l NOTE: The engine now is in the "cooldown " modefor 15 minutes, however, the engine will receive an " auto" fast start signal andgo to a ready-for-load condition upon an SI or A06 Undervoltage condition.
1.6 Note the " green" " READY-FOR-LOAD" light goes out. /
l 1.7 Drain engine air boxes while at idle speed (one valve and pipe plug; volume normally $250 ml). /
1.8 The diesel engine will idle for fifteen minutes before stopping; " amber" light will go out /
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. NUCLEAR POWER BUSINESS UNIT ORT 3 OPERATIONS REFUELING TESTS MAJOR IPTE SAFETY INJECTION ACTUATION WITH LOSS OF Revision 28
/: -
ENGINEERED SAFEGUARDS AC January 25,1997 UNIT 2 TOTAL REWRITE Attachment J G03 / G04 NOTE: Thefuel oil day tank high alarm is set at 90.6 %
1.9 Locally fill the diesel fuel oil day tank T-176A(B) to greater than 86.5% as shown on level indicator LI-3992A(B) by operation of the appropriate fuel oil transfer pump P-206B(P-207B). /
1.10 When the level in the day tank is greater than 86.5%. insure the fuel oil transfer pump control switches are returned to auto. /
1.11 Return the service water pumps to the number required for existing plant ;
conditions (2 minimum). / j 2.0 SECURING THE DIESEL GENERATOR AFTER ORT-3 TEST COMPLETED (DIESEL LOADING REQUIRED).
NOTE: Ensure start is recorded on, " Generator Start and Load Reliability Information Sheet," PBF-2014.
NOTE: Section 2.0 is only required if G03/G04 unloaded run time exceeded four hours during the performance of ORT-3.
1 2.1 Verify the " DIESEL GENERATOR MODE SELECTOR" switch at C-02 is in " AUTO". / l 2.2 Turn "G-03(G-04) DIESEL GENERATOR CONTROL" switch to
" START" at panel C-02 then release. /
- CAUTION
- DO NOT ATTEMPT TO PLACE TWO BREAKER SYNCHRONIZING SWITCHES TO "ON" AT l THE SAME TIME; EACH PARALLELING l OPERATION MUST BE DONE INDEPENDENT l OF OTHERS.
2.3 Turn the synchronizing switch to "ON" for the desired A06 bus breaker.
G03 to l A06 - Bkr I A52-80 /
~ i G04 to 2A06 - Bkr 2A52-93 /
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, , ENGINEERED SAFEGUARDS AC January 25,1997
- UNIT 2 TOTAL REWRITE Attachment J 1 G03 / G04 2.4 Observe the synchronizer voltmeters and synchroscope.
2.4.1 Determine which voltmeter indicates diesel generator output and adjust same to equal or slightly exceed (2 volts or less) that of the normal supply - through operation of the diesel generator
" VOLTAGE REGULATOR CONTROL SWITCH." /
2.4.2 Adjust the diesel generator frequency to obtain synchroscope indication " SLOW IN FAST" direction (2 to 5 RPM) through !
operation of the diesel generator " GOVERNOR CONTROL i SWITCH." /
- CAUTION
- ENSURE THAT THE LOAD ON THE I GENERATOR IS >100 KW, AFTER CLOSING THE NORMAL SUPPLY BREAKER TO l PREVENT REVERSE POWER TRIP.
I NOTE: IfP-32C, D and E are not in service, then they willsequence j "ON" when the output breaker is closed. - l l
2.5 Close the breaker to the desired bus when the synchroscope is just before !
12:00, and within the green band (10*/1.7 min.).
l A06 - Bkr I A52-80 / 4 1
(2A06 - Bkr 2A52-93) /
2.6 Adjust kvars as necessary by operation of the " DIESEL GENERATOR VOLTAGE REGULATOR" control switch. /
2.7 Turn off the synchroscope (synchronizing switch selected in 5.1.5 above placed to "OFF") /
2.8- Open 2SW-2907,1SW-2908,2SW-2907 and 2SW-2908, containment vent cooler outlet valves, as necessary for service water header pressure control. /
~
2.9 Begin one-hour run at 2500-2700 kW and 500 KVARs. /
Page 143 of145 CONTINUOUS USE W .
- . NUCLEAR POWER BUSINESS UNIT ORT 3
- OPERATIONS REFUELING TESTS MAJOR l- IPTE l SAFETY INJECTION ACTUATION WITH LOSS OF Revision 28 '
(g 4 ENGINEERED SAFEGUARDS AC January 25,1997 UNIT 2 TOTAL REWRITE Attachment J i
l G03 / G04
-i, 2.10 Verify that the "MCC B-40 Bus Isolation Bkr. to Non-Safety Loads" !
B52-405M is Closed. /
2.11 Reduce the load to approximately 100kw by adjustment of the " DIESEL GENERATOR GOVERNOR" control switch". /
2.12 Drive kvars to zero with the " DIESEL GENERATOR VOLTAGE REGULATOR" control switch. /
2.13 "OPEN" the diesel generator output breaker to the desired bus:
G03 G04 1 A06 - Bkr 1 A52-80 2A06 - Bkr 2A52-93 2.14 Adjust the frequency and voltage to 60 Hz and 4160 volts respectively. /
t 2.15 Place the "G-03(G-04) DIESEL GENERATOR CONTROL" switch to "STOP" at C-02. /
NOTE: The engine will run at idle speed in the "cooldown " modefor 15 minutes, however, it will receive an autofast start signal andgo to its ready-for-load condition should an SI or A06 Undervoltage condition arise.
2.16 Note the " green" " READY-FOR-LOAD" light goes out. /
2.17 Drain engine air boxes while at idle speed (one valve and pipe plug; volume normally $250 ml). /
2.18 The diesel engine will idle for fifteen minutes before stopping; amber light will go out. /
NOTE: Thefuel oil day tank high alarm is set at 90.6%.
2.19 Locally fill the diesel fuel oil day tank T-176A(B) to greater than 86.5% as shown on level indicator LI-3992A(B) by operation of the appropriate fuel oil transfer pump P-206B(P-207B). .
/
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SAFETY INJECTION ACTUATION WITH LOSS OF Revision 28
/ ENGINEERED SAFEGUARDS AC January 25,1997 UNIT 2 TOTAL REWRITE Attachment J G03 / G04 2.20 When the level in the day tank is greater than 86.5%, insure the fuel oil transfer pump control switches are returned to auto. /
2.21 Return the service water pumps to the number required for existing plant conditions (2 minimum). /
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l Point Beach Nuclear Plant Unit 2 Restart Commitment Summary (February 5,1997)
Commitment ID#: 1 i
l l Commitment Descrintion: Complete a detailed Unit 2 Containment Materiel Condition
- Assessment, addressing housekeeping, system walkdowns, materiel condition, and instrumentation. Extensive work inside Containment was conducted this outage due to I l
the Steam Generator replacement project, so this warrants increased scrutiny during Containment closecut.
Should this assessment identify either generic issues or significant discrepancies which could negatively impact reactor safety, the scope of the assessment will be expanded.
Where discrepancies are identified, appropriate corrective and preventive actions will be taken commensurate with their safety significance.
Completion Timing: This should be completed prior to Unit 2 leaving cold shutdown.
If some systems / components addressed per this commitment are required to be operable before that mode change per Technical Specifications, the applicable portions of this commitment should be completed earlier. ,
Criteria to Closcout This Item:
i
- 1. Completion of the assessment defined in the " Commitment Description" section.
- 2. The Responsible Person has forwarded to the Restart Issues Coordinator:
. A summary of the scope of the materiel condition assessment and when it was ;
conducted (report using the NUTRK system - NUTRK U2R22 RESTART Action
- 1).
- A copy of documentation used to conduct the assessment. ;
e A summary which addresses significant items / issues identified during conduct of the assessment and how they were resolved (can simply reference Condition Report numbers or other tracking mechanisms) OR a statement that there were !
none identified (report using the NUTRK system - NUTRK U2R22 RESTART Action # 1).
- 3. The Restart Issues Coordinator has verified that the: l e Restart issues File includes the documents which the Responsible Person is required to forward to the Restart issues Coordinator (see immediately above).
- Significant items / issues identified during conduct of the assessment are being tracked in a tracking system which is being reviewed per Restart Commitment #20.
1 I
l t
j 4. Completion of an independent verification.
l Status:
This commitment addresses the conditions of systems inside Unit 2 containment. This is l being accomplished through 2 mechanisms:
i e Use of the System Restoration Procedure (NP 2.3.4), which formalizes a systematic approach to restoring systems following extensive work and outages. This procedure has been completed for the RIIR, Reactor Coolant, CVCS, Safety Injection Auxiliary Feedwater, Systems, Diesel Generator, Service Water, ESF, Instrument Air, Diesel Air, ESF, and non-numbered (DA) systems.
. The thorough inspection for materiel condition and operational readiness as part of the proceduralized, normal startup sequence.
Discrepancies identified are being resolved through the Condition Reporting process.
The scheduled completion date is February 25,1997.
I l
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j 2
l i
- Point Beach Nuclear Plant Unit 2 Restart Commitment Summary (February 5,1997)
Commitment ID#: 2 Commitment
Description:
Walkdown all accessible Unit 2 and common Maintenance Rule systems for adequate visual materiel condition. ,
1 Should these walkdowns identify either generic issues or significant discrepancies which could negatively impact reactor safety, the scope of the walkdowns will be expanded. l Where discrepancies are identified, appropriate corrective and preventive actions will be ;
taken commensurate with their safety significance.
Completion Timing: This should be completed prior to Unit 2 leaving cold shutdown.
If some systems / components addressed per this commitment are required to be operable j before that mode change per Technical Specifications, the applicable portions of this ;
commitment should be completed earlier.
Criteria to Closcout This Itinn i
- 1. Completion of the walkdowns defined in the " Commitment Description" section. I
- 2. The Responsible Person has forwarded to the Restart Issues Coordinator:
- A summary of the scope of the walkdowns and when they were conducted (report using the NUTRK system - NUTRK U2R22 RESTART Action # 2).
- A copy of documentation used to conduct the walkdowns.
- A summary which addresses significant items / issues identified during conduct of the walkdowns and how they were resolved (can simply reference Condition Report numbers or other tracking mechanisms) OR a statement that there were none identified (report using the NUTRK system - NUTRK U2R22 RESTART Action # 2).
- 3. The Restart issues Coordinator has verified that the:
e Restart Issues File includes the documents which the Responsible Person is required to forward to the Restart Issues Coordinator (see immediately above).
. Significant items / issues identified during conduct of the walkdowns are being tracked in a tracking system which is being reviewed per Restart Commitment #20.
- 4. Completion of an independent verification.
l 3
Status:
The maintenance rule systems have been identified, and this commitment is being accomplished through two means:
- Most maintenance rule systems are being walked-down using the System Restoration Procedure (NP 2.3.4) outside containment. As of February 5,1997, this procedure has been completed for the RHR, Reactor Coolant, CVCS, Safety injection, Auxiliary Feedwater, Systems, Diesel Generator, Service Water, ESF, Instrument Air, Diesel Air, ESF, and non-numbered (DA) systems.
. The remaining Maintenance Rule systems are being independently walked-down Ibr visual assessment of materiel condition.
Discrepancies identified are being resolved through the Condition Reporting process.
The scheduled completion date is February 25,1997.
4
Point Beach Nuclear Plant Unit 2 Restart Commitment Summary (February 5,1997) l l
Commitment ID#: 3 i
Commitment
Description:
Walkdown all accessible Unit 2 and common systems for ,
outstanding work order tags.
{
Should these walkdowns identify either generic issues or significant discrepancies which i could negatively impact reactor safety, the scope of the walkdowns will be expanded. l Where discrepancies are identified, appropriate corrective and preventive actions will be taken commensurate with their safety significance. l l
Completion Timine: This should be completed prior to Unit 2 leaving cold shutdown. l If some systems / components addressed per this commitment are required to be operable l before that mode change per Technical Specifications, the applicable portions of this commitment should be completed earlier.
Criteria to Closcout This Item:
- 1. Completion of the walkdowns defined in the " Commitment Description" section.
- 2. The Responsible Person has forwarded to the Restart Issues Coordinator:
. A summary of the scope of the walkdowns and when they were conducted (report using the NUTRK system - NUTRK U2R22 RESTART Action # 3).
. A copy of documentation used to conduct the walkdowns.
. A summary which addresses significant items / issues identified during conduct of the walkdowns and how they were resolved (can simply reference Condition Report numbers or other tracking mechanisms) OR a statement that there were none identified (report using the NUTRK system - NUTRK U2R22 RESTART Action # 3).
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- 3. The Restart Issues Coordinator has:
. Verified that the Restart issues File includes the documents which the Responsible Person is required to forward to the Restart issues Coordinator (see immediately above).
. Verified that the significant items / issues identified during conduct of the ;
walkdowns are being tracked in a tracking system which is being reviewed per '
Restart Commitment #20.
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- 4. Completion of an independent verification.
Status:
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As of February 5,1997, this is in progress. It is expected to be completed prior to core loading.
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l Point Beach Nuclear Plant Unit 2 Restart Commitment ,
Summary (February 5,1997)
Commitment ID#: 4 Commitment
Description:
Conduct as-built inspections of the electrical and 12C i components on the Unit 2 CVCS and CCW systems (Work Orders 9607322,9611140, l
9606548, and 9611139). This will ensure that the associated drawings will be accurate. ,
l Should these as-built inspections identify either generic issues o: significant l discrepancies which could negatively impact reactor safety, the scope of the as-built inspections will be expanded. Where discrepancies are identified, appropriate corrective and preventive actions will be taken commensurate with their safety significance. ,
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Completion Timing This should be completed prior to Unh 2 leaving cold shutdown. i Criteria to Closcout This Ittml
- 1. Completion of the as-built inspections associated with the listed work orders.
- 2. The Responsible Person has forwarded the following documentation to the Restart issues Coordinator:
- A copy of page 2 from the closed work orders (the Duty Shift Supervisor's signature and date in the " Equipment Return to Service" section indicates that the associated equipment is operable).
- A summary of the significant items / issues identified during conduct of the work orders and how they were resolved (can simply reference Condition Report numbers or other tracking mechanisms) OR a statement that there were none identified (report using the NUTRK system - NUTRK U2R22 RESTART Action #
4).
- 3. The Restart Issues Coordinator has verified that the:
. Restart Issues File includes the documentation which the Responsible Person is required to forward to the Restart Issues Coordinator (see immediately above).
- Duty Shift Supervisor's signature and date is on the " Equipment Return to Service" section on page 2 of the associated work orders.
- Significant items / issues identified during conduct of the work orders are being tracked in a tracking system which is being reviewed per Restart Commitment #20.
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- 4. Completion of an independent verification. This will verify that:
. Problems identified or created by the activity are captured.
. The scope of work performed reflects the wording of the Restart Commitment. If not, document the rationale for the difference and identify the safety implications.
. Documentation in the Restart File is adequate to support external verification (NRC) activities.
. Appropriate training was completed.
Status:
As of February 5,1997, this item is in the closecut verification process. There were no safety significant issues / discrepancies identified by the Responsible Person.
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Point Beach Nuclear Plant Unit 2 Restart Commitment Summary (February 5,1997)
Commitment ID#: 5 Commitment
Description:
Complete Work Orders 9513222 through 9513225 to conduct inspections of Appendix R alternate power transfer switches.
The inspections will determine whether an E shaped retaining ring on the arcing contact assembly of some ASCO switches is missing. Condition Report 95-602 documents the missing E clip issue. Seismic quali6 cation testing has shown that the switches pass the baseline functional testing even without the E shaped retaining rings installed.
Should these inspections identify either generic issues or significant discrepancies which could negatively impact reactor safety, the scope of the inspections will be expanded.
Where discrepancies are identified, appropriate corrective and preventive actions will be taken commensurate with their safety significance.
Completion Timing: This should be completed prior to Unit 2 leaving cold shutdown.
If some systems / components addressed per this commitment are required to be operable before that mode change per Technical Specifications, the applicable portions of this commitment should be completed earlier.
Criteria to Closcout This Item:
- 1. Completion of the work associated with the listed work orders.
- 2. The Responsible Person has forwarded the following documentation to the Restart issues Coordinator:
- A copy of page 2 from the closed work orders (the Duty Shift Supervisor's signature and date in the " Equipment Return to Service" section indicates that the associated equipment is operable).
- A summary of the significant items / issues identified during conduct of the work orders and how they were resolved (can simply reference Condition Report numbers or other tracking mechanisms) OR a statement that there were none identified (report using the NUTRK system - NUTRK U2R22 RESTART Action #
5).
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l 3. The Restart Issues Coordinator has verified that the:
- Restart Issues File includes the documentation which the Responsible Person is required to forward to the Restart issues Coordinator (see immediately above).
- Duty Shift Supervisor's signature and date is on the " Equipment Return to Sersice" section on page 2 of the associated work orders.
- Significant items / issues identified during conduct of the work orders are being tracted in a tracking system which is being reviewed per Restart Commitment #20.
- 4. Completion of an independent verification. This will verify that:
- Problems identified or created by the activity are captured.
e The scope of wc rk performed reflects the wording of the Restart Commitment. If not, document the rationale for the difference and identify the safety implications.
. Documentation in the Restart File is adequate to support external verification (NRC) activities, e Appropriate training was completed.
Status:
As of February 5,1997, this item is in the closcout verification process. No E-clips were found to be missing.
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l Point Beach Nuclear Plant Unit 2 Restart Commitment ,
Summary (February 5,1997) l Commitment !D#: 6 Commitment
Description:
Complete Work Order 9604151 to perform foreign material exclusion inspections on the Unit 2 4160V safeguards bus 2A-06 and breakers. Debris found in switchgear prompted these inspections.
Should these inspections identify either generic issues or significant discrepancies which could negatively impact reactor safety, the scope of the inspections will be expanded.
Where discrepancies are identified, appropriate corrective and preventive actions will be taken commensurate with their safety significance. l Completion Timing: This should be completed prior to the Unit 2 approach to criticality. )
1 Criteria to Closcout This Itsnu
- 1. Completion of the work associated with the listed work order. :
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- 2. The Responsible Person has forwarded the following documentation to the Restart l Issues Coordinator:
- A copy of page 2 from the closed work order (the Duty Shift Supervisor's signature and date in the " Equipment Return to Service" section indicates that the associated equipment is operable). l
- A summary of the significant items / issues identified during conduct of the work l order and how they were resolved (can simply reference Condition Report numbers '
or other tracking mechanisms) OR a statement that there were none identified (report using the NUTRK system - NUTRK U2R22 RESTART Action # 6).
- 3. The Restart Issues Coordinator has verified that the:
- Restart Issues File includes the documentation which the Responsible Person is required to forward to the Restart Issues Coordinator (see immediately above).
- Duty Shift Supervisor's signature and date is on the " Equipment Return to Service" section on page 2 of the associated work order.
- Significant items / issues identified during conduct of the work order are being tracked in a tracking system which is being reviewed per Restart Commitment #20.
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- 4. Completion of an independent verification. This will verify that:
. Problems identified or created by the activity are captured.
. The scope of work performed reflects the wording of the Restart Commitment. If not, document the rationale for the difference and identify the safety implications.
. Documentation in the Restart File is adequate to support external verification (NRC) activities.
. Appropriate training was completed.
Status:
As of February 5,1997, the work is complete, and this is in the closecut verification process.
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Point Beach Nuclear Plant Unit 2 Restart Commitment Summary (February 5,1997)
Commitment IDA 7 Commitment
Description:
Complete a review of Unit 2 administrative controls implementing or referencing Technical Speci6 cations to ensure Technical Specification requirements are appropriately reflected in the administrative controls.
The scope of this review will be examining the identified documents for accuracy and compliance with requirements, per the criteria in the above paragraph. Should this review identify either generic issues or significant discrepancies which could negatively !
impact reactor safety, the scope of the review will be expanded. Where discrepancies are identined, appropriate corrective and preventive actions will be taken commensurate with their safety significance.
This commitment is also a subset of Enforcement Conference Commitment item # 3.
Completion Timing: This should be completed prior to Unit 2 leaving cold shutdown.
Criteria to Closcout This.llenu
- 1. Completion of the review defined in the " Commitment Description" section.
- 2. The Responsible Person has forwarded a summary to the Enforcement Conference Commitments Coordinator which addresses (report using the NUTRK system):
. When the review occurred.
. Where the Technical Specification requirements are reDected in the administrative controls (i.e., a matrix or equivalent).
. Documents initiated or changed as a result of this review. The identi6 cation number for each of these must be included in this summary, and a copy of those documents sent to the Enforcement Conference Commitments Coordinator.
. Significant items / issues identified during conduct of the review and how they were resolved (can simply reference Condition Report numbers or other tracking mechanisms) OR a statement that there were none identified.
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- 3. The Restart Issues Coordinator or the Enforcement Conference Commitments Coordinator have:
. Verified that the Restart issues File includes the documents which the Responsible Person is required to forward to the Enforcement Conference Commitments Coordinator (see immediately above).
. Verified that the significant items / issues identified during conduct of the review are being tracked in a tracking system which is being reviewed per Restart Commitment #20.
. Coordinated a sampling of the administrative controls reviewed to ensure the reviews were conducted correctly. A summary of the results of that sampling will be included in the Restart issues File.
- 4. Completion of an independent verification.
Status:
As of February 5,1997, this is in progress. This will involve ensuring that all surveillances in Technical Specifications section 15.4 are implemented by plant procedures. In addition, this review will ensure that each surveillance has an associated LCO (from Technical Specifications section 15.3).
The following has been done:
. Obtain existing cross-references which relate Technical Specification surveillances/LCOs to plant procedures, and develop a " master" cross-reference listing.
. Perform an electronic search of all plant procedures for references to Technical Specifications. 648 procedures were identified in this search. All of these procedures have been reviewed and applicable information has been annotated on the master cross-reference listing. j l
The following is in progress:
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. Provide the initial cross-reference information to contractor personnel. Work with the contractor personnel to verify the frequency of surveillance implementation and the accuracy of the " master" cross reference listing.
. Further refine the Technical Specification / procedure " master" cross-reference listing.
. Provide closeout documentation, which includes the Technical Specification /
procedure " master" cross-reference listing, discrepancies identified, and recommendations.
l The scheduled completion date is February 25,1997.
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! l Point Beach Nuclear Plant Unit 2 Restart Commitment i l
Summary (February 5,1997) i I
I Commitment ID#: 8 l C.ommitment
Description:
Review 20% of the Operations Tcchnical Specification, l Inservice Test, and Operations Refueling Test related surveillance procedures, with ;
concentration on those involving major equipment. Upgrade as necessary to include appropriate initial conditions, return to service lineups, properly specified independent verification, reviewing acceptance criteria, and Technical Specification implementation.
The population considered for this commitment will be the Unit 2 and common Operations Technical Specification, Inservice Test, and Operations Refueling Test related surveillance procedures.
The scope of this review will be examining the identified documents for accuracy and compliance with requirements, per the criteria in the above paragraph. Should this review identify either generic issues or significant discrepancies which could negatively
- mpact reactor safety, the scope of the review will be expanded. Where discrepancies are identified, appropriate corrective and preventive actions will be taken commensurate with their safety significance.
The Restart Issues Coordinator will work with the Responsible Person to ensure the l sampling methodology creates a 20% population which is both random and representative -
of the entire population.
1 This commitment is also a subset of Enforcement Conference Commitment item # 17.
Completion Timine: This should be completed prior to Unit 2 leaving cold shutdown.
If some systems / components addressed per this commitment are required to be operable before that mode change per Technical Specifications, the applicable portions of this commitment should be completed earlier.
Criteria to Closcout This Item:
- 1. Completion of the review defined in the " Commitment Description" section.
- 2. The Responsible Person has forwarded a summary to the Enforcement Conference Commitments Coordinator which addresses (report using the NUTRK system):
e When the review occurred.
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. The total number of Operations Technical Specification, inservice Test, and Operations Refueling Test related surveillance procedures.
. Which specific surveillances were reviewed (i.e., the 20%). The surveillance procedure number for each of these must be included in this summary. Also, provide a copy of each changed or created procedure to the Enforcement Conference Commitments Coordinator.
. Surveillances which were changed or created as a result of this review. The surveillance procedure number for each of these must be included in this summary.
Also, provide a copy of each changed or created procedure to the Enforcement Conference Commitments Coordinator.
. Significant items / issues identified during conduct of the review and how they were resolved (can simply reference Condition Report numbers or other tracking mechanisms) OR a statement that there were none identified.
- 3. The Restart issues Coordinator or the Enforcement Conference Commitments Coordinator h we:
. Verified that the Restart Issues File includes the suramary which the Responsible Person is required to forward to the Enforcement Conference Commitments Coordinator.
. Collected and included in the Restart Issues File a copy of each surveillance changed or created as a result of this review.
. Verified that the significant items / issues identified during conduct of the review are being tracked in a tracking system which is being reviewed per Restart Commitment #20.
. Coordinated a sampling of the surveillances reviewed to ensure the reviews were conducted correctly. A summary of the results of that sampling will be included in the Restart issues File.
- 4. Completion of an independent verification.
Status:
As of February 5,1997, three procedures need to be drafted. All others are in the review process. No safety significant issues have been identified thus far.
The scheduled completion date is February 25,1997.
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i Point Beach Nuclear Plant Unit 2 Restart Commitment Summary (February 5,1997)
Commitment ID#: 9 Commitment Descrintiom Review the in Service Testing (IST) acceptance criteria for l the remaining IST pumps (CCW, Charging, Boric Acid Transfer, CR Chill Water, CSR ;
Chill Water, SFP Cooling, and FO Transfer pumps) to ensure that the IST accertance criteria meets the design basis / accident analysis requirements. Make any changes necessary as a result of this review.
The work has already been completed for the SI, RIIR, AFW, SW, and Containment Spray pumps (the original group), so they are not included in this commitment.
The scope of this review will be ensuring that the IST acceptance criteria meets the design basis / accident analysis requirements. Should this review identify either generic issues or significant discrepancies which could negatively impact reactor safety, the scope of the review will be expanded. Where discrepancies are identified, appropriate corrective and preventive actions will be taken commensurate with their safety significance.
This commitment is also Enforcement Conference Commitment item # 39 Completion Timine: This should be completed prior to Unit 2 leaving cold shutdown.
If some systems / components addressed per this commitment are required to be operable before that mode change per Technical Specifications, the applicable portions of this commitment should be completed earlier. i 1
Criteria to Closcout Thislitnu
- 1. Completion of the review defined in the " Commitment Description" section.
- 2. The Responsible Person has forwarded a summary to the Enforcemer.: Conference Commitments Coordinator which addresses (report using the NUTRK system):
. When the review occurred.
. Which specific documents were reviewed. The document number for each of these l must be included in this summary.
{
. Documents initiated or changed as a result of this review. The identification number for each of these must be included in this summary, and a copy of those ,
i documents sent to the Enforcement Conference Commitments Coordinator. l 17 l
e Significant items / issues identified during conduct of the review aiid how they were resolved (can simply reference Condition Report numbers or other tracking mechanisms) OR a statement that there were none identified. ;
- 3. The Restart Issues Coordinator or the Enfbreement Conference Commitments Coordinator have:
. Verified that the Restart Issues File includes the documents which the Responsible ;
Person is required to forward to the Enforcement Conference Commitments !
Coordinator (see immediately above).
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. Verified that the significant items / issues identified during conduct of the review l are being tracked in a tracking system which is being reviewed per Restart l Commitment #20.
. Coordinated a sampling of the documents reviewed to ensure the reviews were conducted correctly. A summary of the results of that sampling will be included in the Restart Issues File.
- 4. Completion of an independent verification.
Status:
Verified closed by the Enforcement Conference Commitments Coordinator. The pumps were all operating satisfactorily. The associated documentation was provided to the NRC in the January 24,1997 weekly management meeting.
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i Point Beach Nuclear Plant Unit 2 Restart Commitment .
Summary (February 5,1997)
Commitment ID#: 10 Commitment
Description:
Review the In Service Testing acceptance criteria for all IST valves to ensure that the IST acceptance criteria meets the design basis / accident analysis ;
l requirements. Complete necessary operability evaluations, revise procedures, and resolve Unit 2 equipment discrepancies.
The scope of this review will be examining the associated docurnents for accuracy and compliance with requirements, per the criteria in the above paragraph. Should this j review identify either generic issues or significant discrepancies which could negatively 1 impact reactor safety, the scope of the review will be expanded. Where discrepancies are ;
identified, appropriate corrective and preventive actions will be taken commensurate with !
their safety significance. l l
I This commitment is also Enfnrcement Conference Commitment item # 40.
Completion Tindngt This will be completed prior to January 17,1997. Ifsome systems / components addressed per this commitment are required to be operable before l that mode change per Technical Specifications, the applicable portions of this !
commitment should be completed earlier.
Criteria to Closcout This Item:. i, i
- 1. Completion of the review defined in the " Commitment Description" section.
- 2. The Responsible Person has forwarded a summary to the Enforcement Conference Commitments Coordinator which addresses (report using the NUTRK system):
. When the review occurred.
. Identification of which valves which are in the IST Program. l
. Which specific documents were reviewed. The document number for each of these must be included in this summary.
)
. Documents initiated or changed as a result of this review. The identification i number for each of these must be included in this summary, and a copy of those I I
documents sent to the Enforcement Conference Commitments Coordinator.
. Significant items / issues identified during conduct of the review and how they were resolved (can simply reference Condition Report numbers or other tracking mechanisms) OR a statement that there were none identified.
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- 3. The Restart Issues Coordinator or the Enforcement Conference Commitments Coordinator have:
. Verified that the Restart Issues File includes the documents which the Responsible Person is required to forward to the Enforcement Conference Commitments Coordinator (see immediately above).
. Verified that the significant items / issues identified during conduct of the review are being tracked in a tracking system which is being reviewed per Restart Commitment #20.
. Coordinated a sampling of the documents reviewed to ensure the reviews were conducted correctly. A summary of the results of that sampling will be included in the Restart issues File.
- 4. Completion of an independent verification.
Status:
Verified closed by the Enforcement Conference Commitments Coordinator. The associated documentation was provided to the NRC in the January 24,1997 weekly management meeting.
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Point Beach Nuclear Plant Unit 2 Restart Commitment Summary (February 5,1997)
Commitment ID#: 11 Commitment
Description:
Complete the following regarding installed instrumentation used in the IST program: :
- Identify the Unit 2 installed instruments used in the IST program. ,
e Review the performance of the identified instruments over the last 3 years. j e Review the suitability of the instrumentation for use in the IST program. !
- Review all IST pump hydraulic data over the past year for adverse trends.
As necessary, make changes as a result of these actions.
Should these reviews identify either generic issues or significant discrepancies which l could negatively impact reactor safety, the scope of the reviews will be expanded. Where discrepancies are identified, appropriate corrective and preventive actions will be taken commensurate with their safety significance.
This commitment is also Enforcement Conference Commitment Item # 43.
Completion Timine: This should be completed prior to Unit 2 leaving cold shutdown. 1 If some systems / components addressed per this commitment are required to be operable j before that mode change per Technical Specifications, the applicable portions of this l commitment should be completed earlier.
Criteria to Closcout This Item; 1
- 1. Completion of the reviews defined in the " Commitment Description" section.
- 2. The Responsible Person has forwarded a summary to the Enforcement Conference Commitments Coordinator which addresses (report using the NUTRK system):
e When the reviews occurred.
- Identification of the Unit 2 installed instruments used in the IST program.
- Documents initiated or changed as a result of these reviews. The identification number for each of these must be included in this summary, and a copy of those ,
documents sent to the Enforcement Conference Commitments Coordinator. '
- Results of the reviews.
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e Significant items / issues identified during conduct of the reviews and how they were resolved (can simply reference Condition Report numbers or other tracking mechanisms) DR a statement that there were none identified.
- 3. The Restart Issues Coordinator or the Enforcement Conference Commitments Coordinator have verified that the:
- Restart Issues File includes the documents which the Responsible Person is required to forward to the Enforcement Conference Commitments Coordinator (see immediately above).
- Significant items / issues identified during conduct of the reviews are being tracked in a tracking system which is being reviewed per Restart Commitment #20,
- 4. Completion of an independent verification.
Status:
Verified closed by the Enforcement Conference Commitments Coordinator. The associated documentation was provided to the NRC in the January 24,1997 weekly management meeting.
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i Point Beach Nuclear Plant Unit 2 Restart Commitment Summary (February 5,1997)
Commitment ID#: 12 Commitment Descriptism Review 20% of the surveillance procedures associated with safety significant non-pump and valve components (such as heat exchangers and fans) to ensure that the surveillance acceptance criteria satisfy the requirements of the plant design basis / accident analysis. Make changes as necessary as a resuit of this review.
The population considered for this commitment will be the Unit 2 and common surveillance procedures associated with safety significant non-pump and valve components (such as heat exchangers and fans).
The scope of this review will be examining the identified documents for accuracy and compliance with requirements, per the criteria in the above paragraph. Should this review identify either generic issues or significant discrepancies which could negatively ;
impact reactor safety, the scope of the review will be expanded. Where discrepancies are identified, appropriate corrective and preventive actions will be taken commensurate with i their safety significance. l The Restart Issues Coordinator will work with the Responsible Person to ensure the j sampling methodology creates a 20% population which is both random and representative )
of the entire population.
This commitment is also Enforcement Conference Commitment item # 47.
Completion Timine: This should be completed prior to Unit 2 leaving cold shutdown.
If some systems / components addressed per this commitment are required to be operable before that mode change per Technical Specifications, the applicable portions of this commitment should be completed earlier.
Criteria to Closcout This Item:
- 1. Completion of the review defined in the " Commitment Description" section.
- 2. The Responsible Person has forwarded a summary to the Enforcement Conference Commitments Coordinator which addresses (report using the NUTRK system):
. When the review occurred.
- The total number of surveillance procedures associated with safety significant non-i pump and valve components (such as heat exchangers and fans). The surveillance procedure number for each of these must be included in this summary.
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t I e Which specine surveillances were reviewed (i.e., the 20%). The surveillance l procedure number for each of these must be included in this summary.
. Surveillances which were changed or created as a result of this review. The surveillance procedure number for each of these must be included in this summary. ,
e Significant items / issues identified during conduct of the review and how they were l resolved (can simply reference Condition Report numbers or other tracking mechanisms) OR a statement that there were none identined.
- 3. The Restart issues Coordinator or the Enforcement Conference Commitments Coordinator have:
. Verified that the Restart Issues File includes the summary which the Responsible Person is required to fonvard to the Enforcement Conference Commitments Coordinator (see immediately above).
- Collected and included in the Restart Issues File a copy of each surveillance changed or created as a result of this review. ,
e Verined that the signincant items / issues identified during conduct of the review l are being tracked in a tracking system which is being reviewed per Restart Commitment #20. ;
e Coordinated a sampling of the surveillances reviewed to ensure the reviews were I conducted correctly. A summary of the results of that sampling will be included in the Restart Issues File. l
- 4. Completion of an independent verification.
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Status:
As of February 5,1997, this is in progress. A review of 20% (8 of 36 tests) of the !
surveillance procedures associated with safety significant non-pump and valve components was completed on January 20,1997. Two Condiden Reports has been written. The scope of this effort has increased to complete the revew of all Unit 2 and common surveillance procedures associated with safety significant nan-pump and valve !
components prior to Unit 2 restart. This will include the generic reactor engineering l procedures.
The scheduled completion date is February 14,1997.
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l l Point Beach Nuclear Plant Unit 2 Restart Commitment l Summary (February 5,1997)
Commitment ID#: 13 Commitment
Description:
Review other operating procedures that contain maintenance activities and revise as necessary to ensure PMT and QC are properly addressed by those procedures. This will be done for Unit 2 operating procedures.
The scope of this review will be examining the identined documents for accuracy and compliance with requirements, per the criteria in the above paragraph. Should this review identify either generic issues or significant discrepancies which could negatively impact reactor safety, the scope of the review will be expanded. Where discrepancies are identiDed, appropriate corrective and preventive actions will be taken commensurate with their safety significance. l l
This commitment is also Enforcement Conference Commitment Item # 51.
Completion Timine: This will be completed prior to January 31,1997. Ifsome systems / components addressed per this commitment are required to be operable before j that mode change per Technical Specifications, the applicable portions of this j commitment should be completed earlier. l Criteria to Closcout This Item:
- 1. Completion of the review defined in the " Commitment Description" section. .
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- 2. The Responsible Person has forwarded a summary to John Palmer (the Enforcement Conference Commitments Coordinator) which addresses (report using the NUTRK system):
. When the review occurred.
. Which specific operating procedures were reviewed. The operating procedure number for each of these must be included in this summary. Send a copy of the index review checklists to the Enforcement Conference Commitments Coordinator.
. Documents initiated or changed as a result of this review. The identification number for each of these must be included in this summary, and a copy of those documents sent to the Enforcement Conference Commitments Coordinator.
. Significant items / issues identified during conduct of the review and how they were l resolved (can simply reference Condition Report numbers or other tracking mechanisms) OR a statement that there were none identified.
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- 3. The Restart Issues Coordinator or the Enforcement Conference Commitments Coordinator have:
. Verified that the Restart Issues File includes the documents which the Responsible Person is required to fonvard to Enforcement Conference Commitments Coordinator (see immediately above).
. Verified that the significant items / issues identified during conduct of tic. review are being tracked in a tracking system which is being reviewed per Restart Commitment #20.
. Coordinated a sampling of the operating procedures reviewed to ensure the reviews were conducted correctly. A summary of the results of that sampling will be included in the Restart Issues File.
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- 4. Completion of an independent verification.
Status:
As of February 5,1997, the work is completed, and this is in the independent verification process. The review was conducted by Point Beach operations personnel and contractors.
781 procedures were reviewed for maintenance activities. Of these, a total of 70 procedures were determined to require revision (67 for PMT; 15 for QC). Condition Reports have been submitted for the 70 procedures to vidress operability determinations.
Changes have been submitted for 53 of the 70 procedures The other 17 procedures will be controlled via a temporny change process which ensures that the procedures will not be used until reviewed for QC and PMT.
- All of the following procedure types were reviewed: 01, OP, TS, IT, PC, and RF. l e RP series procedures excepting RP-7 and RP-8 were reviewed (those will be so l reviewed and revised prior to the next ISFSI cask load). Procedure holds have been placed on these to ensure they are not used before.
. Unit 1 ORT procedures excepting 3,3A,3B,3C,9 (and appendices),10, and 17 (those will be so reviewed and revised prior to the next use). Procedure holds have been placed on these to ensure they are not used before.
- Unit 2 ORT procedures excepting ORT 3 A and 3Il (those will be so reviewed and revised prior to the next use) and ORT 9 (and appendices),10, and 17 (those will be so reviewed and revised prior to Unit 2 restart). Procedure holds have been placed on these to ensure they are not used before.
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h Point Beach Nuclear Plant Unit 2 Restart Commitment Summary (February 5,1997) ,
l Commitment ID#: 14 l
l Commitment Descrintion: Review equipment return to service testing requirements i l prior to the following U2R22 mode change readiness reviews to ensure the required l equipment is operable prior to changing the following modes: core reload, leaving cold shutdown, and the approach to criticality, i
Should this review identify either generic issues or significant discrepancies which could negatively impact reactor safety, the scope of the review will be expanded. Where discrepancies are identified, appropriate corrective and preventive actions will be taken commensurate with their safety significance.
l This commitment is also Enforcement Conference Commitment Item # 53.
Completion Timing: This will be completed prior to core loading, prior to leaving cold shutdown, and prior to the approach to criticality.
Criteria to Closcout This Item:
- 1. Completion of the three reviews defined in the " Commitment Description" section.
- 2. The Responsible Person has forwarded a summary to the Enforcement Conference Commitments Coordinator which addresses (report using the NUTRK system):
. When the reviews occurred.
. Copies of documents used to perform the reviews.
. Results of the reviews.
. Significant items / issues identified during conduct of the review and how they were resolved (can simply reference Condition Report numbers or other tracking mechanisms) OR a statement that there were none identified.
- 3. The Restart Issues Coordinator or the Enforcement Conference Commitments Coordinator have verified that the:
. Restart issues File includes the documents which the Responsible Person is required to forward to the Enforcement Conference Commitments Coordinator (see immediately above).
. Significant items / issues identified during conduct of the reviews are being tracked in a tracking system which is being reviewed per Restart Commitment #20.
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- 4. Completion of an independent verification.
Status:
The readiness review checklists associated with each of the three mode changes are drafted, and they are being updated as new issues are identified. The readiness reviews will occur shortly before each of the three major mode changes (core loading, leaving cold shutdown, and the approach to criticality).
These reviews are scheduled activities in the Major Item Work List and are
" predecessors" to each plant condition.
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Point Beach Nuclear Plant Unit 2 Restart Commitment Summary (February 5,1997) l Commitment ID#: 15 Commitment
Description:
Review 20% of the work orders performed since January 1, 1995 on Unit 2 or common PSA safety significant systems (AFW, SW, EDG, I A,4.16 kv, gas turbine, and CCW) to verify adequate PMT was performed to ensure system / component safety function.
Approximately 80% of the work orders at Point Beach Nuclear Plant are maintenance work orders, and the original commitment focused on maintenance work orders alone. l The scope of this review has been expanded to address the non-maintenance work orders l also. 1 The scope of this review will be examining the identified documents for accuracy and j compliance with requirements, per the criteria in the above paragraph. Should this review identify either generic issues or significant discrepancies which could negatively impact reactor safety, the scope of the review will be expanded. Where discrepancies are identified, appropriate corrective and preventive actions will be taken commensurate with I their safety significance.
The Restart Issues Coordinator will work with the Responsible Person to ensure the sampling methodology creates a 20% population which is both random and representative i of the entire population. l Completion Timine: This should be completed prior to Unit 2 leaving cold shutdown.
If some systems / components addressed per this commitment are required to be operable before that mode change per Technical Specifications, the applicable portions of this commitment should be completed earlier.
Criteria to Closcout This Item:
- 1. Completion of the review defined in the " Commitment Description" section.
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- 2. The Responsible Person has f^nvarded a summary to the Restart Issues Coordinator which addresses (report using the NUTRK system - NUTRK U2R22 RESTART Action # 15):
. When the review occurred.
. The total number of work orders performed since January 1,1995 on Unit 2 or l j common PSA safety significant systems (AFW, SW, EDO,lA,4.16 kv, gas l
29 i
l turbine, and CCW). The work order number fbr each of these must be included in this summary.
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. Which specific work orders were reviewed (i.e., the 20%). The work order number for each of these must be included in this summary.
. Work orders and other documents initiated or changed as a result of this review.
The identification number for each of these must be included in this summary, and a copy of those documents sent to the Restart issues Coordinator for inclusion in the Restart Issues File (for the work orders, only forward pages 1 and 2).
. Significant items / issues identified during conduct of the review and how they were resolved (can simply reference Condition Report numbers or other tracking mechanisms) DR a statement that there were none identified.
- 3. The Restart Issues Coordinator has:
. Verified that the Restart Issues File includes the documents which the Responsible Person is required to forward to the Restart Issues Coordinator (see immediately above).
. Verified that the significant items / issues identified during conduct of the review are being tracked in a tracking system which is being reviewed per Restart Commitment #20.
. Coordinated a sampling of the work orders reviewed to ensure the reviews were conducted correctly. A summary of the results of that sampling will be included in the Restart Issues File.
- 4. Completion of an independent verification.
Status:
As of February 5,1997, this is in progress.
. A ten person QA team is conducting the review.
. 397 of 1944 work orders have been selected for review. This review has been completed.
. Condition Reports are being written for discrepancies found.
This is scheduled to be completed by February 10,1997.
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Point Beach Nuclear Plant Unit 2 Restart Commitment Summary (February 5,1997)
Commitment ID#: 16 Commitment Descriptiont Complete all Unit 2 Maintenance Rule related work order post-PMT reviews prior to the approach to criticality. ;
The scope of this review will be examining the identified documents for accuracy and I compliance with requirements, per the criteria in the above paragraph. Should this i review identify either generic issues or significant discrepancies which could negatively !
impact reactor safety, the scope of the review will be expanded. Where discrepancies are identified, appropriate corrective and preventive actions will be taken commensurate with !
their safety significance.
Completion Timine: This should be completed prior to the Unit 2 approach to criticality.
Criteria to Closcout This Item:
- 1. Completion of the reviews defined in the " Commitment Description" section.
- 2. The Responsible Person has forwarded a summary to the Restart Issues Coordinator which addresses (report using the NUTRK system - NUTRK U2R22 RESTART Action # 16):
. When the reviews occurred.
. Which specific work orders were reviewed. The work order number for each of these must be included in this summary.
- Documents initiated or changed as a result of these reviews. The identification number for each of these must be included in this summary, and a copy of those documents sent to the Restart Issues Coordinator for inclusion in the Restart Issues File.
. Significant items / issues identified during conduct of the reviews and how they were resolved (can simply reference Condition Report numbers or other trackine mechanisms) OR a statement that there were none identified.
- 3. The Restart Issues Coordinator has:
. Verified that the Restart Issues File includes the documents which the Responsible Person is required to forward to the Restart Issues Coordinator (see immediately above).
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1 e Verified that the significant items / issues identified during conduct of the reviews are being tracked in a tracking system which is being reviewed per Restart Commitment #20.
. Coordinated a sampling of the work orders reviewed to ensure the reviews were l conducted correctly. A summary of the results of that sampling will be included in the Restart issues File.
- 4. Completion of an independent verification. i 1
Status: l i
As of February 5,1997, the review is in progress, occurring as work orders become available.
As this is a continuous process, the scheduled completion date for this commitment will coincide with the approach to criticality.
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i Point Beach Nuclear Plant Unit 2 Restart Commitment !
Summary (February 5,1997) l l
l Commitment ID#: 17 '
l Commitment Descriptinm Review 50.59 screenings conducted in 1996. Upgrade those l
determined to require a 50.59 evaluation. This will be done for all 50.59 screenings, not !
just those involving Unit 2.
1 During November 1996, QA auditors reviewed the 50.59 and 72.48 safety evaluation processes per QA audit A-P-96-17. The auditors reviewed two hundred 50.59 screenings and identified six which required a full 50.59 evaluation and another six which were ;
questionable. None of these were found to involve an Unreviewed Safety Question. l l
The scope of this review will be examining the identified documents for accuracy and j compliance with requirements. Should this review identify either generic issues or significant discrepancies which could negatively imr . reactor safety, the scope of the i review will be expanded. Where discrepancies are iaentified, appropriate corrective and preventive actions will be taken commensurate with their safety significance.
Completion Timine: This should be completed prior to the Unit 2 approach to criticality. If some systems / components addressed per this commitment are required to be operable before that mode change per Technical Specifications, the applicable portions of this commitment should be completed earlier.
Criteria to Closcout This Item:
- 1. Completion of the review defined in the " Commitment Description" section. ;
- 2. The Responsible Person has forwarded a summary to the Restart Issues Coordinator i which addresses (report using the NUTRK system - NUTRK U2R22 RESTART Action # 17):
- When the review occurred.
- How many screenings were reviewed.
- Documents initiated or change i as a result of this review (this includes 50.59 evaluations). The identification number for each of these must be included in this summary, and a copy of those documents sent to the Restart Issues Coordinator fbr inclusion in the Restart Issues File.
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- Significant items / issues identified during conduct of the review and how they were l resolved (can simply reference Condition Report numbers or other tracking mechanisms) OR a statement that there were none identified.
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- 3. 'I he Restart Issues Coordinator has: l i
e Verified that the Restart Issues File includes the documents which the Responsible j Person is required to forward to the Restart Issues Coordinator (see immediately j above).
- Verified that the significant items / issues identified during conduct of the review ,
are being tracked in a tracking system which is being reviewed per Restart l
Commitment #20. ;
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- Coordinated a sampling of the 50.59 screenings reviewed to ensure the reviews l
were conducted correctly. A summary of the results of that sampling will be ;
included in the Restart Issues File.
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- 4. Completion of an independent verification.
Status: ;
As of February 5,1997, the review has been completed of all screenings done from (
January 1,1996 to present (over 400 screenings). 21 screenings are being upgraded to ;
50.59 evaluations, and 4 screenings are being re-written due to lack of detail. No USQs have been identified.
This is scheduled to be complete by February 20,1997.
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Point Beach Nuclear Plant Unit 2 Restart Commitment Summary (February 5,1997)
Commitment ID#: 18 Commitment
Description:
Review outstanding JCOs. Perform operability determinations and 50.59 evaluations needed to address the issues. This applies to all outstanding JCOs, not just the ones associated with Unit 2.
The scope of this review will be examining the outstanding JCOs for accuracy and compliance with requirements. Should this review identify either generic issues or significant discrepancies which could negatively impact reactor safety, the scope of the review will be expanded. Where discrepancies are identified, appropriate corrective and preventive actions will be taken commensurate with their safety significance.
Completion Timing: This should be completed prior to Unit 2 leaving cold shutdown.
Criteria to Closcout This Item:
- 1. Completion of the review defined in the " Commitment Description" section.
- 2. The Responsible Person has forwarded a summary to the Restart Issues Coordinator which addresses (report using the NUTRK system - NUTRK U2R22 RESTART Action # 18):
. When the review occurred.
. Which specific JCOs were reviewed.
. Documents initiated or changed as a result of this review (including operability determinations and 50.59 evaluations). The identification number for each of these I must be included in this summary, and a copy of those documents sent to the i Restart Issues Coordinator for inclusion in the Restart Issues File.
. Significant items / issues identified during conduct of the review and how they were resolved (can simply reference Condition Report numbers or other tracking l mechanisms) D.R a statement that there were none identified.
- 3. The Restart issues Coordinator has:
e Verified that the Restart Issues File includes the documents which the Responsible Person is required to forward to the Restart issues Coordinator (see immediately j above).
. Verified that the significant items / issues identified during conduct of the review are being tracked in a tracking system which is being reviewed per Restart i
Commitment #20.
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. Coordinated a sampling of the JCOs reviewed to ensure the reviews were conducted correctly. A summary of the results of that sampling will be included in the Restart Issues File.
- 4. Completion of an independent verification.
Status:
As of February 5,1997, there are three outstanding JCOs:
JCO #94-03 -involves DC Molded Case Circuit Breakers. A 50.59 will be written for this, and a team is investigating. There was one operability issue identified with wire separation which could impact molded case circuit breakers. That operability issue is being dispositioned through the CR and operability determination processes.
. JCO #94-07 -involves the Containment Accident Fan motor unshielded bearings. A 50.59 evaluation has been drafted and is being reviewed.
. JCO #96 involves Containment Fan Cooler operation during a Design Basis Accident. The associated 50.59 evaluation involves a USQ, for which documentation has been provided to the NRC (Technical Specification Change Request 192).
This is scheduled to be complete by February 21,1997.
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Point Beach Nuclear Plant Unit 2 Restart Commitment l Summary (February 5,1997) l l
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Commitment ID#: 19 Commitment
Description:
Conduct a review of 50.59 evaluations from this outage. I Ensure all conditions of the evaluations have been completed. This review will address the 50.59 evaluations for Unit 2.
The scope of this review will be examining the identified documents for accuracy and I compliance with requirements, per the criteria in the above paragraph. Should this review identify either generic issues or significant discrepancies which could negatively impact reactor safety, the scope of tl.e review will be expanded. Where discrepancies are identified, appropriate corrective and preventive actions will be taken commensurate with j their safety significance.
Completion Timine: This should be completed prior to Unit 2 leaving cold shutdown. ;
I If some systems / components addressed per this commitment are required to be operable before that mode change per Technical Specifications, the applicable portions of this commitment should be completed earlier.
1 Criteria to Closcout This Item: ,
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- 1. Completion of the review defined in the " Commitment Description" section. l
- 2. The Responsible Person has forwarded a summary to the Restart issues Coordinator which addresses (report using the NUTRK system - NUTRK U2R22 RESTART Action # 19):
. When the review occurred.
. A listing of the 50.59 evaluations which were reviewed.
. Documents initiated or changed as a result of this review. The identification number for each of these must be included in this summary, and a copy of those documents sent to the Restart Issues Coordinator for inclusion in the Restart Issues File.
. Results of the review.
. Significant items / issues identified during conduct of the review and how they were resolved (can simply reference Condition Report numbers or other tracking mechanisms) OR a statement that there were none identified. j 1
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- 3. The Restart Issues Coordinator has:
1
! . Verified that the Restart issues File includes the documents which the Responsit:1e Person is required to forward to the Restart Issues Coordinator (see immediately above).
. Verified that the significant items / issues identified during conduct of the review are being tracked in a tracking system which is being reviewed per Restart Commitment #20.
. Coordinated a sampling of the 50.59 evaluations reviewed to ensure the reviews were conducted correctly. A summary of the results of that sampling will be included in the Restart Issues File.
- 4. Completion of an independent verification.
Status:
As of February 5,1997, this is in progress. There are two aspects of this:
. To identify existing outage related 50.59 evaluations, all 50.59 cvaluations from January 1,1996 to current were reviewed to identify the outage related population.
From that population,18 commitments were identified, which are being tracked to completion through the outage. j
. As additional outage related 50.59 evaluations are developed, commitments are being l identified and tracked to completion through the outage. l l
As this is a continuous process, the scheduled completion date for this commitment will l coincide with the approach to criticality.
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Point Beach Nuclear Plant Unit 2 Restart Commitment Summary (February 5,1997) ,
Commitment ID#: 20 I Commitment
Description:
Review items from existing open item lists (e.g., NUTRK) !
to identify potentially degraded equipment. Other lists which could identify potentially degraded equipment must also be reviewed per this commitment, including informal lists [
in peoples' desks, etc. i I
Should this review identify either generic issues or significant discrepancies which could !
negatively impact reactor safety, the scope of the review will be expanded. Where discrepancies are identified, appropriate corrective and preventive actions will be taken :
commensurate with their safety significance.
Completion Timing: This should be completed prior to Unit 2 leaving cold shutdown.
If some systems / components addressed per this commitment are required to be operable before that mode change per Technical Specifications, the applicable portions of this commitment should be completed earlier. ,
Criteria to Closcout This Item:
- 1. Completion of the review defined in the " Commitment Description" section.
- 2. Each Group Ilead has informed the Restart Issues Coordinator:
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. That the review described in the " Commitment Description" section has been completed for their group.
. What potentially degraded equipment was identified from their review (reference a
)
NUTRK identification number, etc. to uniquely identify the document addressing the issue).
- 3. The Restart Issues Coordinator has:
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. Verified that the Group Ileads have reported the data listed immediately above (in item 2).
- Distributed a listing of the documents reported to him which identify potentially I degraded equipment, so that the issues can be addressed. l
. Coordinated a sampling of the items reviewed to ensure the reviews were conducted correctly. A summary of the results of that sampling will be included in the Restart Issues File.
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- 4. Completion of an independent verification.
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Status:
As of February 5,1997, this review is in progress.
l A targeted review was conducted of all outstanding Condition Reports by a team l composed of a Mechanical System Supervisor, an Electrical /I&C System Engineer, and a DSS. This review resulted in a listing of Condition Reports which are potential operability concerns or startup issues.
Emergent Condition Reports will be reviewed to identify those involving potentially degraded equipment, and those will be added to the listing of Condition Reports which are potential operability concerns or startup issues l
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Point Beach Nuclear Plant Unit 2 Restart Commitment i Summary (February 5,1997) !
1 Commitment ID#: 21 ;
Commitment
Description:
Review open items from the Design 11 asis Document development program. i The scope of this review will be examining the identified documents for accuracy and l compliance with requirements. Should this review identify either generic issues or !
significant discrepancies which could negatively impact reactor safety, the scope of the !
4 review will be expanded. Where discrepancies are identified, appropriate corrective and l l
preventive actions will be taken commensurate with their safety significance. I Completion Timine: This should be completed prior to Unit 2 leaving cold shutdown.
If some systems / components addressed per this commitment are required to be operable 3 before that mode change per Technical Specifications, the applicable portions of this
- commitment should be completed earlier.
Criteria to Closcout This Item:
- 1. Completion of the review defined in the " Commitment Description" section.
- 2. The Responsible Person has fbrwarded a summary to the Restart issues Coordinator which addresses (report using the NUTRK system - NUTRK U2R22 RESTART j Action # 21):
. When the review occurred.
- Which specific open DI3D items were reviewed.
. Documents initiated or changed as a result of this review. The identification number for each of these must be included in this summary, and a copy of those documents sent to the Restart Issues Coordinator for inclusion in the Restart Issues File.
- Significant items / issues identified during conduct of the review and how they were resolved (can simply reference Condition Repon numbers or other tracking mechanisms) DR a statement that there were none identified.
- 3. The Restart Issues Coordinator has verified that the:
- Restart Issues File includes the documents which the Responsible Person is required to forward to the Restart issues Coordinator (see immediately above).
41
e Significant items / issues identified during conduct of the review are being tracked in a tracking system which is being reviewed per Restart Commitment #20.
- 4. Completion of an independent verification.
Status:
As of February 5,1997, this has been reported as. complete by the Responsible Person.
Closcout documentation (per section 2 above) is being prepared.
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! Point Beach Nuclear Plant Unit 2 Restart Commitment l Summary (February 5,1997)
Commitment ID#: 22 Commitment
Description:
All open operability evaluations for Unit 2 and common equipment will be reviewed for acceptable closure of the degraded equipment issue. i Disposition outstanding issues in accordance with 10CFR50.59 and Generic Letter 91-18.
The scope of this review will be examining the identified documents for accuracy and compliance with requirements, per the criteria in the above paragraph. Should this !
review identify either generic issues or significant discrepancies which could negatively impact reactor safety, the scope of the review will be expanded. Where discrepancies are identified, appropriate corrective and preventive actions will be taken commensurate with their safety significance.
Completion Timine: This should be completed prior to Unit 2 leaving cold shutdown. '
If some systems / components addressed per this commitment are required to be operable before that mode change per Technical Specifications, the applicable portiors of this commitment should be completed earlier. ,
2 Criteria to Closcout This Item: ,
- 1. Completion of the review defined in the " Commitment Description" section.
- 2. The Responsible Person has forwarded a summary to the Restart Issues Coordinator :
which addresses (report using the NUTRK system - NUTRK U2R22 RESTART l Action # 22): l e When the review occurred.
- Which specific open operability evaluations were reviewed.
- Documents initiated or changed as a result of this review. The identification number for each of these must be included in this summary, and a copy of those documents sent to the Restart issues Coordinator for inclusion in the Restart issues File.
- Significant items / issues identified during conduct of the review and how they were l resolved (can simply reference Condition Report numbers or other tracking j mechanisms) OR a statement that there were none identified.
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- 3. The Restart Issues Coordinator has:
. Verified that the Restart Issues File includes the documents which the Responsible Person is required to forward to the Restart Issues Coordinator (see immediately ,
above). !
. Verified that the significant items / issues identified during conduct of the review i are being tracked in a tracking system which is being reviewed per Restart Commitment #20.
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. Coordinated a sampling of the open operability evaluations reviewed to ensure the reviews were conducted correctly. A summary of the results of that sampling will be included in the Restart Issues File.
- 4. Completion of an independent verification.
Status:
As of February 5,1997, this review is in progress.1065 records have been reviewed by a multidisciplinary team (an NSSS Mechanical Engineering Supervisor, a senior Electrical /
I&C Engineer, and a DSS) to identify open operability determinations. Of the 1065 records:
1 1
e 107 were initially dispositioned as definitely appearing to constitute a startup issue (RED).
. I16 were initially dispositioned as requiring further review. ;
e 822 were initially dispositioned as definitely not a startup issue.
For those determined to constitute a startup issue, the issue will either be completely resolved or a 50.59 evaluation will be completed documenting acceptability of the i situation prior to Unit 2 startup. i l
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Point Beach Nuclear I'lant Unit 2 Restart Commitment Summary (February 5,1997)
Commitment ID#: 23 Commitment
Description:
Review 20% of the Condition Reports closed since January 1,1995 which are associated with PSA safety significant systems for degraded equipment operability issues to ensure that we have adequately identified and dispositioned i operability issues. This commitment applies to all Condition Reports, not simply those applicable to Unit 1.
The scope of this review will be examining the identified documents for accuracy and compliance with requirements, per the criteria in the above paragraph. Should this i review identify either generic issues or significant discrepancies which could negatively impact reactor safety, the scope of the review will be expanded. Where discrepancies are !
identified, appropriate corrective and preventive actions will be taken commensurate with l their safety significance. i The Restart Issues Coordinator will work with the Responsible Person to ensure the sampling methodology creates a 20% population which is both random and representative of the entire population. l i
Completion Timine: This should be completed prior to Unit 2 leaving cold shutdown. l If some systems / components addressed per this commitment are required to be operable before that mode change per Technical Specifications, the applicable portions of this ;
commitment should be completed earlier. !
Criteria to Closcout This Item:
- 1. Completion of the review defined in the " Commitment Description" section.
- 2. The Respomible Person has forwarded a summary to the Restart issues Coordinator ,
which addresses (report using the NUTRK system - NUTRK U2R22 RESTART l
Action # 23): i
. When the review occurred.
. The total number of Condition Reports closed since January 1,1995 which are i associated with PSA safety significant systems.
. Which specific Condition Reports were reviewed (i.e., the 20%). The Condition !
Report number for each of these must be included in this summary. l
. Documents initiated or changed as a result of this review. The identification number for each of these must be included in this summary, and a copy of those 45
documents sent to the Restart Issues Coordinator for inclusion in the Restart Issues l'ile.
. Signific uit items / issues identified during canduct of the review and how they were resolved (can simply reference Condition Report numbers or other tracking mecha.iisms) OR a statement that there were none identified.
- 3. The Restart Issues Coordinator has:
. Verified that the Restart Issues File includes the documents which the Responsible Person is required to forward to the Restart Issues Coordinator (see immediately above).
. Verified that the significant items / issues identified during conduct of the review are being tracked in a tracking system which is being reviewed per Restart Commitment #20.
. Coordinated a sampling of the Condition Reports reviewed to ensure the review was conducted correctly. A summa >y of the results of that sampling will be included in the Restart Issues File.
- 4. Completion of an independent verification.
Status:
As of February 5,1997, the review is in progress.
This is scheduled to be completed by February 7,1997.
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l Point Beach Nuclear Plant Unit 2 Restart Commitment Summary (February 5,1997) ,
Commitment ID#: 24 Commitment
Description:
Complete an additional Outage Safety Review for the l startup phase of the outage. This will evaluate the remainder of the outage schedule from a nuclear safety perspective, not a scheduling perspective.
l Should this review identify either generic issues or significant discrepancies which could l
negatively impact reactor safety, the scope of the review will be expanded. Where discrepancies are identified, appropriate corrective and preventive actions will be taken commensurate with their safety significance.
Completion Timing: This should be completed prior to the Unit 2 core loading.
Criteria to Closcout This Item:
- 1. Completion of the review defined in the " Commitment Description" section. I
- 2. The Responsible Person has forwarded a summary to the Restart issues Coordinator which addresses (report using the NUTRK system - NUTRK U2R22 RESTART Action # 24):
- When the review occurred.
= A description of what was reviewed.
- Documents initiated or changed as a result of this review. The i&ntification number for each of these must be included in this summary, and a copy of those documents sent to the Restart issues Coordinater for inclusion in the Restart Issues File.
. Significant items / issues identified during conduct of the review and how they were resolved (can simply reference Condition Report numbers or other tracking mechanisms) OR a statement that there were none identified.
- 3. The Restart Issues Coordinator has verified that the:
- Restart Issues File includes the documents which the Responsible Person is required to forward to the Restart Issues Coordinator (see immediately above).
- Significant items / issues identified during conduct of the review are being tracked in a tracking system which is being reviewed per Restart Commitment #20.
- 4. Completion of an independent verification.
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l Status:
i This review was initiated on February 5,1997.
i This is scheduled to be completed by February 10,1997.
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Point Beach Nuclear Plant Unit 2 Restart Commitment Summary (February 5,1997)
Commitment ID#: 25 Commitment
Description:
Conduct an integrated review of all outage licensing commitments (50.59's, enforcement conference items, Technical Specification Change Requests, and the Reload Safety Analysis). Ensure all requirements are met.
The scope of this review will be to identify outstanding licensing commitment issues which need to be resolved prior to mode changes. Those issues will then be appropriately resolved. Should this review identify either generic issues or signincant discrepancies which could negatively impact reactor safety, the scope of the review will be expanded.
Where discrepancies are identified, appropriate corrective and preventive actions will be taken commensurate with their safety significance. I Completion Timine: This should be completed prior to Unit 2 leaving cold shutdown.
Criteria to Closcout This Item: j
- 1. Completion of the review defined in the " Commitment Description" section. )
- 2. The Responsible Person has forwarded a summary to the Restart Issues Coordinator which addresses (report using the NUTRK system - NUTRK U2R22 RESTART Action # 25):
. When the review occurred.
. A description of what was reviewed.
- A list of the outstanding licensing commitment issues that need to be resolved prior to mode changes.
. Significant items / issues identified during conduct of the review and how they were resolved (can simply reference Condition Report numbers or other tracking mechanisms) QR a statement that there were none identified.
- 3. The Restart Issues Coordinator has verified that the:
- Restart issues File includes the documents which the Responsible Person is required to fonvard to the Restart issues Coordinator (see immediately above).
- Significant items / issues identified during conduct of the review are being tracked in a tracking system which is big reviewed per Restart Commitment #20.
49
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- 4. Completion of an independent verification.
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As of February 5,1997, the review has been conducted, and minutes from that meeting have been finalized. A list ofrequirements for the mode changes has been developed and is being followed through the outage.
l This is scheduled to be complete by February 28,1997.
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Point Beach Nuclear Plant Unit 2 Restart Commitment Summary (February 5,1997)
Commitment ID#: 26 Commitment
Description:
Revise ORT-3 and DCS 3.1.11 to ensure Technical Specification 15.4.6.A.2 testing includes dynamic loading of the EDG with sequenced loads.
Completion Timine: This should be completed prior to the Unit 2 core loading.
Criteria to Closcout This item:
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- 1. Completion of the actions defined in the " Commitment Description" section.
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- 2. The Responsible Person has forwarded to the Restart issues Coordinator:
- A copy of the revised ORT-3 and DCS 3.1.11. !
. A summary which addresses significant items / issues identified during conduct of ;
this task and how they were resolved (can simply reference Condition Report numbers or other tracking mechanisms) OR a statement that there were none identified (report using the NUTRK system - NUTRK U2R22 RESTART Action
- 26).
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- 3. The Restart Issues Coordinator has verified that the:
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. Restart Issues File includes the documents which the Responsible Person is :
required to forward to the Restart Issues Coordinator (see immediately above). j e Significant items / issues identified during conduct of the task are being tracked in a tracking system which is being reviewed per Restart Commitment #20.
- 4. Completion of an independent verification.
Status:
As of February 5,1997, the work has been completed, and this is in the closeout verification process. l 1
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Point Beach Nuclear Plant Unit 2 Restart Commitment Summary (February 5,1997)
Commitment ID#: 27 l
Commitment Descrintion: Test all EDGs in accordance with revised ORT-3 and DCS-3.1.11. Return the electrical systems to normal alignment prior to leaving cold shutdown. !
Where discrepancies are identified, appropriate corrective and preventive actions will be ,
taken commensurate with their safety significance.
Completion Timing: This should be completed prior to the Unit 2 core loading.
Criteria to Closcout This Item:
- 1. Completion of the actions defined in the " Commitment Description" section.
- 2. The Responsible Person has forwarded a summary to the Restart Issues Coordinator which addresses (report using the NUTRK system - NUTRK U2R22 RESTART j Action # 27):
. When the actions defined in the " Commitments Description" section were completed.
. Significant items / issues identified during conduct of this task and how they were resolved (can simply reference Condition Report numbers or other tracking mechanisms) OR a statement that there were none identified.
- 3. The Restart issues Coordinator has verified that the:
- Restart Issues File includes the documents which the Responsible Person is l required to forward to the Restart Issues Coordinator (see immediately above).
. Significant items / issues identified during conduct of the task are being tracked in a tracking system which is being reviewed per Restart Commitment #20.
- 4. Completion of an independent verification.
Stalun As of February 5,1997, ORT-3 testing has been initiated.
This is scheduled to be completed by February 7,1997.
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Point Beach Nuclear Plant Unit 2 Restart Commitment i Summary (February 5,1997)
Commitment ID#: 28 i Commitment
Description:
Resolve the containment penetration commitments, including:
. CP-32C (Containment penetration for auxiliary charging line). A small leak (4 drops !
per minute at 1900 psig) was found in the 3/4 inch Si test line (CPP-32B). This was documented on Condition Report 97-0003.
. Penetration thermal reliefissue. This issue concerns the potential for overpressurization of piping passing through containment, the result causing a loss of containment integrity. For this to be a concern, the piping must be water-solid and :
isolated by two non-relieving containment isolation valves. Condition Report 96-470 was initiated regarding this following an industry operating experience item from Maine Yankee, which was followed-up by IN 96-049 and Generic Letter 96-06. The l PBNP initial response to the Generic Letter was sent to the NRC under VPNPD l 090.
Should generic issues or significant discrepancies be identified during this resolution which could negatively impact reactor safety, the scope of this effort will be expanded.
Where discrepancies are identified, appropriate corrective and preventive actions will be taken commensurate with their safety. significance.
Completion Timine: This should be completed prior to Unit 2 leaving cold shutdown.
Criteria to Closcout This Item:
- 1. Resolution of the containment penetration commitments dermed in the " Commitment Description" section.
- 2. The Responsible Person has forwarded a summary to the Restart Issues Coordinator l which addresses (report using the NUTRK system - NUTRK U2R22 RESTART Action # 28):
- When the actions described in the " Commitments Description" section were completed.
. What specifically was done to resolve the containment penetration commitments.
. Documents initiated or changed as a result of this task. The identification number for each of these must be included in this summary, and a copy of those documents sent to the Restart Issues Coordinator for inclusion in the Restart Issues File.
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! e Signi5 cant items / issues identified during conduct of this task and how they were resolved (can simply reference Condition Report numbers or other tracking j mechanisms) DR a statement that there were none identified.
l 3. The Restart Issues Coordinator has verified that the:
- Restart Issues File includes the documents which the Responsible Person is required to forward to the Restart Issues Coordinator (see immediately above).
. Significant items' issues identified during conduct of the task are being tracked in a tracking system which is being reviewed per Restart Commitment #20.
- 4. Completion of an independent verification.
Status:
As of February 5,1997:
Unit 2 Penetration 32 - containment penetration 32 was full of water due to a leak in the SI test line (CPP-32B in CIIAMPS). The leak rate was approximately 4 drops per minute at 1950 psig. The site of the leak was at the weld where the SI test line is welded to the penetration cap on the inside of containment. To complete repairs, both the Si test line and auxiliary charging line (CPP-32C) piping sections that pass through penetration 32 were replaced per % tk Order 96-13591. The penetration envelope was leak-tested with air to ensure integrity of the pipe-to-penetration cap welds. A hydrostatic test of the auxiliary charging line and the SI test line has been successfully completed.
Similar Unit 2 containment penetrations were inspected and found to be intact, so this is i not considered a generic problem. A work order has been initiated to perform these same inspections during UlR24 Penetration thermal reliefissue - the concern is being evaluated under Condition Report 96-470 (also identified by IN 96-049 and GL 96-06) by Mike Woznicki. The following lines were identified as concerns by the evaluation:
- P-11 (RCP seal water return line)- operability for Unit I required 2 inches of callsil insulation inside containment. Insulation was installed per Work Order 9700318. A four-hour NRC event notification was made concerning this on Unit 1, and an I.ER is being submitted. For Unit 2, a modification is being prepared which will install a reli f valve on this line, probably outside containment, to provide overpressure protection. Potential overpressure concerns also exist for the Si test line (P-32B) and the pressurizer liquid sample line (P-28B). Evaluation of these concerns is on-going.
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- P-12A (DI water supply line)- The Unit 1 D1 water supply line has been drained twice. Three gallons drained out the first time, and four ounces was drained one week later. The line will be checked again to ensure that valve leak-by does not cause the line to become water-solid. For Unit 2, CL-1B is being revised to ensure the DI water supply line does not become water-solid during power operation. This will result in one PAB D1 hose station being removed from service. An associated 50.59 evaluation is presently under review and is planned for MSS presentation on january 30,1997. As a long-term solution, modifications will be required to allow isolating P-12A piping without causing a loss of DI water to other components.
. P-30C (Pressuri<er relief tank makeup)- this line is protected by air operated diaphram valves, so no modification is necessary.
- P-32C (Auxiliary charging line)- this line is protected by air operated CV-1296, so no modification is required.
. P-53 (licating steam condensate return)-this line was verified not water-solid on Unit
- 1. For Unit 2, this line is being cut and weld-capped per modification 96-068 during U2R22.
This is scheduled to be completed by February 21,1997.
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Point Beach Nuclear Plant Unit 2 Restart Commitment Summary (February 5,1997) l Commitment ID#: 29 l
Commitment
Description:
Complete a 50.59 evaluation for the existing CCW supply to the RCP seals as a safety function. In 1992, Point Beach Nuclear Plant committed to making this configuration consistent with the classification of that function as a safety function. This is already classified as safety related from a pressure boundary standpoint, but not for the flow function.
Should this evaluation identify either generic issues or significant discrepancies which could negatively impact reactor safety, the scope of this effort will be expanded. Where discrepancies are identified, appropriate corrective and preventive actions will be taken commensurate with their safety significance.
Completion Timine: This should be completed prior to Unit 2 leaving cold shutdown.
Criteria to Closcout This Item:
- 1. Completion of the 50.59 evaluation.
- 2. The Responsible Person has forwarded to the Restart issues Coordinator:
. A copy of the completed 50.59 cvaluation.
. A summary which addresses significant items / issues identified during conduct of this task and how they were resolved (can simply reference Condition Report numbers or other tracking mechanisms) OR a statement that there were none identified (report using the NUTRK system - NUTRK U2R22 RESTART Action
- 29).
- 3. The Restart issues Coordinator has verified that the:
. Restart Issues File includes the documents which the Responsible Person is )
required to forward to the Restart Issues Coordinator (see immediately above). l
. Significant items / issues identified during conduct of the task are being tracked in a tracking system which is being reviewed per Restart Commitment #20.
- 4. Completion of an independent verification.
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Status:
l As of February 4,1997, we are re-evaluating whether using a 50.59 evaluation to complete this commitment is appropriate, as there seems to be no change to trigger its use. This had been recognized that it was a new use for a 50.59 evaluation (evaluating a present configuration versus the traditional use of evaluating a proposed modification).
This is scheduled to be completed by February 10,1997.
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Point Beach Nuclear Plant Unit 2 Restart Commitment j Summary (February 5,1997) :
Commitment ID#: 30 Commitment Descriptiom Update the diesel generator loading calculation N-91-016 to properly reflect the loading of the Containment Fan Coolers.
Where discrepancies are identified, appropriate corrective and preventive actions will be taken commensurate with their safety significance.
Completion Timing: This should be completed prior to Unit 2 leaving cold shutdown.
Criteria to Closcout This Item:
- 1. Completion of the diesel generator loading calculation task update defined in the
" Commitment Description" section. ;
- 2. The Responsible Person has forwarded to the Restart Issues Coordinator:
- A copy of the revised coverpage to the diesel generator loading calculation N 016 and the page showing the new reference (#61). i e A summary which addresses significant items / issues identified during conduct of I this task and how they were resolved (can simply reference Condition Report l numbers or other tracking mechanisms) QR a statement that there were none identified (report using the NUTRK system - NUTRK U2R22 RESTART Action
- 30).
- 3. The Restart Issues Coordinator has verified that the:
. Restart Issues File includes the documents which the Responsible Person is required to forward to the Restart Issues Coordinator (see immediately above). ,
e Significant items / issues identified during conduct of the task are being tracked in a I tracking system which is being reviewed per Restart Commitment #20.
- 4. Completion of an independent verification. !
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i Status:
As of February 5,1997:
. An original calculation could not be located, so it was thought that this task was necessary. That calculation has since been found, so the diesel generator loading calculation only needs to be revised to add that reference calculation.
. The loading calculation has been updated to add that reference calculation. Ilowever, questions have arisen concerning the validity of the CFC loading values used, and that is being investigated.
The scheduled completion date is February 15,1997 l
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Point Beach Nuclear Plant Unit 2 Restart Commitment ;
Summary (February 5,1997) l Commitment ID#: 31 Commitment
Description:
Evaluate the adequacy of coordination on the 120 VAC i instrument bus system through a 50.59 evaluation or operability determination.
i Should this evaluation identify either generic issues or significant discrepmcies which could negatively impact reactor safety, the scope of the evaluation will be expanded. I Where discrepancies are identified, appropriate corrective and preventive actions will be taken commensurate with their safety significance.
I Completion Timing: This should be completed prior to Unit 2 leaving cold shutdown. l I
Criteria to Closcout This Item:
- 1. Completion of the evaluation / operability review defined in the " Commitment Description" section.
- 2. The Responsible Person has forwarded to the Restart Issues Coordinator:
. A copy of the 50.59 evaluation or operability determination.
. A summary which addresses significant items / issues identified during conduct of this task and how they were resolved (can simply reference Condition Report numbers or other tracking mechanisms) DR a statement that there were none identified (report using the NUTRK system - NUTRK U2R22 RESTART Action
- 31).
- 3. The Restart issues Coordinator has verified that the:
. Restart Issues File includes the documents which the Responsible Person is required to forward to the Restart Issues Coordinator (see immediately above).
. Significant items / issues identified during conduct of the task are being t:acked in a tracking system which is being reviewed per Restart Commitment #20.
- 4. Completion of an independent verification.
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l Status:
As of February 5,1997:
- Modifications have been initiated to re-supply non-safety rehted panels 2Yl1,2Y21, 2Y31, and 2Y41 from non-safety related supplies.
- A formal calculation is being performed to determine the fault currents at the inverters to evaluate whether the current limit will be reached. Following this, an operability determination or a 50.59 evaluation will be completed.
The scheduled completion date is February 15,1997.
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Point Beach Nuclear Plant Unit 2 Restart Commitment Summary (February 5,1997) l Commitment ID#: 32 Commitment
Description:
Implement interim improvements for the Condition Reporting process, based on a review of assessments and identified recommendations for improving that process.
Completion Timing: This will be completed prior to the Unit 2 approach to criticality.
Criteria to Closcout This Item:
- 1. Completion of the implementation ofinterim improvements for the Condition Reporting process defined in the " Commitment Description" section.
- 2. The Responsible Person has forwarded to the Restart Issues Coordinator:
- A copy of the interim improvements for the Condition Reporting process.
. A summary which addresses significant items / issues identified during conduct of this task and how they were resolved (can simply reference Condition Report numbers or other tracking mechanisms) DR a statement that there were none l identified (report using the NUTRK system - NUTRK U2R22 RESTART Action
- 32).
- 3. The Restart Issues Coordinator has verified that the:
l
- Restart Issues File includes the documents which the Responsible Person is ;
required to forward to the Restart issues Coordinator (see immediately above). l
- Significant items / issues identified during conduct of the task are being tracked in a tracking system which is being reviewed per Restart Commitment #20.
- 4. Completion of an independent verification.
Satun As of February 5,1997:
- A staff review of current Condition Reports has been instituted immediately l following the morning update.
. The next step will be to couple th<.: Condition Report review and the Operating Experience review into e sing!;, daily meeting which will be attended by personnel l
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from several disciplines. Some staff members will also attend. This was implemented on January 27,1997.
. Additional actions are being evaluated.
This is scheduled to be complete by February 25,1997.
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! Point Beach Nuclear Plant Unit 2 Restart Commitment .
! Summary (February 5,1997)
Commitment ID#: 33 .
Commitment
Description:
Implement interim improvements for the 50.59 process to require that all screenings be either authored or reviewed by a member of the multi- j disciplinary review team.
Completion Timine: This will be completed prior to the Unit 2 approach to criticality. !
i Criteria to Closcout This Ittml
- 1. Completion of the implementation ofinterim improvements for the 50.59 process defined in the " Commitment Description" section.
- 2. The Responsible Person has forwarded to the Restart Issues Coordinator. i l
e A copy of the interim improvements for the 50.59 process.
. A summary which addresses significant items / issues identified during conduct of this task and how they were resolved (can simply reference Condition Report i numbers or other tracking mechanisms) QR a statement that there were none l identified (report using the NUTRK system - NUTRK U2R22 RESTART Action I
- 33).
- 3. The Restart Issues Coordinator has verified that the:
. Restart issues File includes the documents which the Responsible Person is required to forward to the Restart issues Coordinator (see immediately above).
- Significant items / issues identified during conduct of the task are being tracked in a tracking system which is being reviewed per Restart Commitment #20.
- 4. Completion of an independent verification. l i
Status:
As of February 5,1997, this is in progress:
- Members for the multi-disciplinary review team have been designated.
l . Training for these personnel will be conducted by John Jaeckle in early February to l ensure consistency in their approach.
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. This will assure that no-evaluation screenings are in fact no-evaluation screenings.
The existing full, in-line review team will still exist, The interim ing .,vements will be included in NP 10.3.1.
The scheduled completion date is February 13,1997, f
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i Point Beach Nuclear Plant Unit 2 Restart Commitment Summary (February 5,1997) 1 Commitment ID#: 34
! Commitment Descriptinm Upgrade Unit 2 operations checklists to include i requirements for initials, time, and date. During the review, verify that the checklists are i technically correct.
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Should this upgrade identify either generic issues or significant discrepancies which
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could negatively impact reactor safety, the scope of the upgrade will be expanded. Where ;
l discrepancies are identified, appropriate corrective and preventive actions will be taken l commensurate with their safety significance. l This is also a subset of Enforcement Conference Commitment Item # 18.
Completion Timing: This should be completed prior to Unit 2 leaving cold shutdown.
If some systems / components addressed per this commitment are required to be operable before that mode change per Technical Specifications, the applicable portions of this commitment should be completed earlier.
Criteria to Closcout This Item:
- 1. Completion of the actions defined in the " Commitment Description" section.
- 2. The Responsible Person has forwarded to the Enforcement Conference Commitments Coordinator:
- A listing of which Unit 2 operations checklists were reviewed, with an indication of which were revised (report using the NUTRK system).
- A copy of each revised Unit 2 operations checklist.
- A summary which addresses significant items / issues ;dentified during conduct of this task and how they were resolved (can simply reference Condition Report numbers or other tracking mechanisms) OR a statement that there were none identified (report using the NUTRK system).
- 3. The Restart Issues Coordinator has verified that the:
e Restart Issues File includes the documents which the Responsible Person is required to forward to the Enforcement Conference Commitments Coordinator (see immediately above).
- Significant items / issues identified during conduct of the task are being tracked in a j tracking system which is being reviewed per Restart Commitment #20.
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- 4. Completion of an independent verification.
Status:
As of February 5.1997, there are two checklists remaining to be updated.
This is scheduled to be completed by February 19,1997.
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Point Beach Nuclear Plant Unit 2 Restart Commitment Summary (February 5,1997) !
Commitment ID#: 35 Commitment
Description:
Revise applicable IST program documents to prevent equipmer' from being returned to service (declared operable) with vibrations in the alert range.
Should this revision effort identify either generic issues or significant discrepancies which could negatively impact reactor safety, the scope of the effort will be expanded.
Where discrepancies are identified, appropriate corrective and preventive actions will be taken commensurate with their safety significance.
This commitment is also Enforcement Conference Commitment item # 41.
Completion Timing: This should be completed prior to Unit 2 leaving cold shutdown.
Criteria to Closcout This Item:
- 1. Completion of the actions defined in the " Commitment Description" section. ,
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- 2. The Responsible Person has forwarded to the Enforcement Conference Commitments Coordinator:
. A copy of the revised IST program documents.
. A summary which addresses significant items / issues identified during conduct of !
this task and how they were resolved (can simply reference Condition Report l numbers or other tracking mechanisms) OR a statement that there were none identified (report using the NUTRK system).
- 3. The Restart Issues Coordinator has wrified that the:
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. The Restart Issues File includes the documents which the Responsible Person is
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required to forward to the Enforcement Conference Commitments Coordinator (see l immediately above).
. Significant items / issues identified during conduct of the task are being tracked in a l
tracking system which is being reviewed per Restart Commitment #20.
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- 4. Completion of an independent verification.
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Statun As of February 5,1997, the work has been completed, and this is in the closcout verification process.
The revision to OM 4.2.2 provides guidance for returning a Section XI pump back to service following maintenance. Specifically, no pump will be returned to service following maintenance with a vibration greater than 0.325 ips.
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Point Beach Nuclear Plant Unit 2 Restart Commitment Summary (February 5,1997) i Commitment ID#: 36 Commitment
Description:
Revise NP 8.1.1, Work Order Processing, and NP 8.1.3, Post-Maintenance Testing, to ensure post-maintenance testing, operability testing, and surveillance testing requirements are properly addressed.
This commitment is also Enforcement Conference Commitment item # 57.
Completion Timina: This should be completed prior to the Unit 2 approach to criticality.
Criteria to Closcout This Item:
- 1. Completion of the actions defined in the " Commitment Description" section.
- 2. The Responsible Person has forwarded to the Enforcement Conference Commitments Coordinator:
- A copy of the revised documents. !
e A summary which addresses significant items / issues identified during conduct of l
this task and how they were resolved (can simply reference Condition Report l numbers or other tracking mechanisms) OR a statement that there were none identified (report using the NUTRK system).
- 3. The Restart Issues Coordinator has verified that the:
- Restart Issues File includes the documents which the Responsible Person is required to forward to the Enforcement Conference Commitments Coordinator (see immediately above).
. Significant items / issues identified during conduct of the task are being tracked in a tracking system which is being reviewed per Restart Commitment #20.
- 4. Completion of an independent verification.
Status:
I As of February 5,1997, the work has been completed, and this is in the closecut I verification process. NP 8.1.1 was revised. Changes to NP 8.1.3 were not necessary, as l this procedure references NP 8.1.1 for content.
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s Point Beach Nuclear Plant Unit 2 Restart Commitment Summary (February 5,1997) '
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l Commilment ID#: 37 Commitment
Description:
Include return to service testing in the plant schedule, botn outage and nonoutage.
This commitment is also Enforcement Conference Commitment item # 59.
Completion Timing: This should be completed prior to the Unit 2 core loading.
Criteria to Closcout This Item:
- 1. Completion of the actions defined in the " Commitment Description" section.
- 2. The Responsible Person has forwarded to the Enforcement Conference Commitments Coordinator:
- A copy of a plant schedule with the return to service testing included.
. A copy of plant procedures changed to implement these.
- The date this task was accomplished (report using the NUTRK system).
. A summary which addresses significant items / issues identified during conduct of this task and how they were resolved (can simply reference Condition Report numbers or other tracking mechanisms) OR a stat: ment that there were none identified (report using the NUTRK system).
- 3. The Restart Issues Coordinator has verified that the:
- Restart issues File includes the documents which the Responsible Person is required to forward to the Enforcement Conference Commitments Coordinator (see immediately above).
- Significant items / issues identified during conduct of the task are being tracked in a tracking system which is being reviewed per Restart Commitment #20.
- 4. Completion of an independent verification.
Stalun I As of February 5,1997, the work has been completed, and this is in the closcout verification process.
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l Point Beach Nuclear Plant Unit 2 Restart Commitment !
Summary (February 5,1997) l 1
Cmluullment ID#: 38 Cmumhment Description; The following modification will be in an accepted status (i.e., the applicable physical work completed, post-maintenance and return to service testing completed satisfactorily, and the associated component / system being declared operable) prior to being required to be operable per Technical Specifications:
Modification 96-033 - replace control power transfomiers on Motor Control Centers 2B32 and 2B42.
These control power transformers were identified as being relatively undersized. This modification will replace the approximately 60 existing Unit 2 control power transformers with larger ones to increase the margin for performing their function.
There are approximately 30 common control power transformers associated with this ,
modification which will be replaced af ter U2R22, during a system outage or when the !
equipment is not required.
Completion Timing: This should be in an accepted status prior to the Unit 2 core j loadmg. i Criteria to Closcout This Item: l
- 1. The modification is in an accepted status. 1
- 2. The Responsible Person has forwarded the following documentation to the Restart issues Coordinator:
- A copy of the Installation Work Package page which shows the Duty Shift Supervisor's acceptance of the modification.
- A summary of the significant items / issues identified during conduct of the modification and how they were resolved (.can simply reference Condition Report numbers or other tracking mechanisms) OR a statement that there were none identified (report using the NUTRK system - NUTRK U2R22 RESTART Action #
38).
- 3. The Restart Issues Coordinator has verified that:
- The Restart Issues File includes the documentation which the Responsible Person is required to forward to the Restart Issues Coordinator (see immediately above).
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i e The Duty Shift Supervisor's signature and date is on the copy of the Installation Work Package page.
The significant items / issues identified during conduct of the modification are being tracked in a tracking system which is being reviewed per Restart Commitment #20.
- 4. Completion of an independent verification. This will verify that:
- Problems identified or created by the activity are captured.
. The safety evaluation reflects the scope of work completed.
. The scope of work performed reflects the wording of the Restart Commitment. If i
not, document the rationale for the difference and identify the safety implications. i e Documentation in the Restart File is adequate to support extemal verification (NRC) activities.
- Appropriate training was completed.
. Procedure updates identified in the modification package were completed.
1 Status:
As of February 4,1997, this is in progress.
The scheduled completion (acceptance) date is February 15,1997.
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l Point Beach Nuclear Plant Unit 2 Restart Commitment Summary (February 5,1997)
Commitment ID#: 39 Commitment
Description:
The following modification will be in an accepted status (i.e., the applicable physical work completed, post-maintenance and return to service testing completed satisfactorily, and the associated component / system being declared operable) prior to being required to be operable per Technical Specifications:
Modification 90-048 - replace Boric Acid and Reactor Makeup Water totalizers, replace the CVCS control switch, replace flow indicators, and refurbish flow controllers.
Due to their unreliability when operating in automatic, these controls have been used in the manual mode. This resolves a workaround issue.
Completion Timine: This should be in an accepted status prior to the Unit 2 core loading.
Criteria to Closcout This item:
- 1. The modification is in an accepted status.
- 2. The Responsible Person has fbrwarded the following cocumentation to the Restart Issues Coordinator:
- A copy of the Installation Work Package page which shows the Duty Shift Supervisor's acceptance of the modification.
- A summary of the significant items / issues identified during conduct of the modification and how they were resolved (can simply reference Condition Report ,
numbers or other tracking mechanisms) DR a statement that there were none identified (report using the NUTRK system - NUTRK U2R22 RESTART Action #
39).
- 3. The Restart Issues Coordinator has verified that the:
- Restart issues File includes the documentation which the Responsible Person is required to forward to the Restart Issues Coordinator (see immediately above). ;
- Duty Shift Supervisor's signature and date is on the copy of the Installation Work l Package page.
- Significant items / issues identified during conduct of the modification are being tracked in a tracking system which is being reviewed per Restart Commitment #20.
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- 4. Completion of an independent verification. This will verify that:
. Problems identified or created by the activity are captured.
. The safety evaluation reflects the scope of work completed.
. The scope of work performed reflects the wording of the Restart Commitment. If not, document the rationale for the difference and identify the safety implications.
. Documentation in the Restart File is adequate to support external verification (NRC) activities.
- Appropriate training was completed.
. Procedure updates identified in the modification package were completed.
fitains As of February 5,1997, the PMT has been completed satisfactorily. This modification is awaiting verification of procedure updates, equipment labeling, and updates to Control Room drawings. No problems were identified during the conduct of this modification.
The scheduled completion (acceptance) date is February 7,1997.
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Point Beach Nuclear Plant Unit 2 Restart Commitment Summary (February 5,1997)
Commitment ID#: 40 Contmittnent
Description:
The following modification will be in an accepted status (i.e., the applicable physical work completed, post-maintenance and return to service testing completed satisfactorily, and the associated component / system being declared operable) prior to being required to be operable per Technical Specifications: !
Modification 94-097 - remove six RCS loop drain valves.
i These valves are radiological hot spots and potential leakage paths. Due to leakage from l one of these valves, the unit was forced to shutdown. Maintenance draindowns can be i performed from other loop drain valves.
Completion Timing: This will be in an accepted status immediately after the RCS leak check, per Technical Specification 15.4.3.
Criteria to Closcout This Ittnu
- 1. The modification is in an accepted status.
- 2. The Responsible Person has forwarded the following documentation to the Restart issues Coordinator:
- A copy of the Installation Work Package page which shows the Duty Shift Supervisor's acceptance of the modification.
. A summary of the significant items / issues identified during conduct of the modification and how they were resolved (can simply reference Condition Report numbers or other tracking mechanisms) QR a statement that there were none identified (report using the NUTRK system - NUTRK U2R22 RESTART Action #
40).
- 3. The Restart issues Coordinator has verified that the:
- Restart Issues File includes the documentation which the Responsible Person is required to forward to the Restart issues Coordinator (see immediately above).
- Duty Shift Supervisor's signature and date is on the copy of the Installation Work Package page.
- Significant items / issues identified during conduct of the modification are being tracked in a tracking system which is being reviewed per Restart Commitment #20.
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- 4. Completion of an independent verification. This will verify that:
- Problems identified or created by the activity are captured.
. The safety evaluation reflects the scope of work completed.
. The scope of work perfonned reflects the wording of the Restart Commitment. If not, document the rationale for the difference and identify the safety implications.
. Documentation in the Restart File is adequate to support external verification (NRC) activities.
. Appropriate training was completed.
. Procedure updates identified in the modification package were completed.
Status:
As of February 5,1997, the physical work has been completed, and the modification is awaiting PMT (completion of the RCS leak test).
The scheduled completion (acceptance) date is February 28,1997.
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l Point Beach Nuclear Plant Unit 2 Restart Commitment Summary (February 5,1997)
Commitattnt ID#: 41 Commitment
Description:
The following modification will be in an accepted status (i.e., the applicable physical work completed, post-maintenance and return to service testing completed satisfactorily, and the associated component / system being declared operable) prior to being required to be operable per Technical Specifications:
Modification 92-141 - relocate the RilR tiow control valve controllers on 2CO3 for human factoring.
Train "A" and train "B" main control board controls typically have a left to right '
convention on Unit I and a right to left convention on Unit 2. This convention was not followed for the RIIR controllers 211C-624 and 2HC-625, and this modification corrects that. Also, the common flow controller 211C-626 will be positioned between these two RIIR controllers to improve their separation.
Completion Timine: This should be in an accepted status prior to the Unit 2 core ,
loading. I Criteria to Closcout This Item: )
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- 1. The modification is in an accepted status.
- 2. The Responsible Person has forwarded the following documentation to the Restart Issues Coordinator:
. A copy of the Installation Work Package page which shows the Duty Shift Supervisor's acceptance of the modification.
. A summary of the significant items / issues identified during conduct of the I modification and how they were resolved (can simply reference Condition Report l numbers or other tracking mechanisms) OR a statement that there were none identified (report using the NUTRK system - NUTRK U2R22 RESTART Action #
4 l).
- 3. The Restart Issues Coordinator has verified that the:
- Restart Issues File includes the documentation which the Responsible Person is required to forward to the Restart Issues Coordinator (see immediately above).
- Duty Shift Supervisor's signature and date is on the copy of the Installation Work l l Package page.
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l e Significant items / issues identified during conduct of the modification are being l
l tracked in a tracking system which is being reviewed per Restart Commitment #20.
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l 4. Completion of an independent verincation. This will verify that:
. Problems identified or created by the activity are captured.
. The safety evaluation reflects the scope of work completed.
. The scope of work performed reflects the wording of the Restart Commitment. If not, document the rationale for the difference and identify the safety implications.
. Documentation in the Restart File is adequate to support external verification (NRC) activities.
. Appropriate training was completed.
. Procedure updates identified in the modification package were completed.
Status:
As of February 5,1997, this item is in the closecut verification process. The work was completed per Work Order 9605772.
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Point Beach Nuclear Plant Unit 2 Restart Commitment Summary (February 5,1997) l Commitment ID#: 42 Commitment
Description:
The following modification will be in an accepted status (i.e., the applicable physical work completed, post-maintenance and return to sen ice testing completed satisfactorily, and the associated component / system being declared i operable) prior to being required to be operable per Technical Specifications:
Modification 96-073 - seismically upgrade CCW, SI, RilR, and RilR/ letdown piping supports and remove an AFW snubber.
Completion Timingt This should be in an accepted status prior to the Unit 2 core loading.
CIiftria to Cintnut This Item:
i
- 1. The modification is in an accepted status. i
- 2. The Responsible Person has forwarded the following documentation to the Restart i Issues Coordinator-l
. A copy of the Installation Work Package page which shows the Duty Shift ;
Supervisor's acceptance of the modification.
. A summary of the significant items / issues identified during conduct of the modification and how they were resolved (can simply reference Condition Report l numbers or other tracking mechanisms) OR a statement that there were none identified (report using the NUTRK system - NUTRK U2R22 RESTART Action #
42).
- 3. The Restart Issues Coordinator has verified that the:
. Restart Issues File includes the documentation which the Responsible Person is required to forward to the Restart issues Coordinator (see immediately above).
. Duty Shift Supervisor's signature and date is on the copy of the Installation Work Package page.
. Significant items / issues identified during conduct of the modification are being tracked in a tracking system which is being reviewed per Restart Commitment #20.
- 4. Completion of an independent verification. This will verify that:
. Problems identified or created by the activity are captured.
. The safety evaluation reflects the scope of work completed.
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e The scope of work performed reflects the wording of the Restart Commitment. If not, document the rationale for the difference and identify the safety implications.
. Documentation in the Restart File is adequate to support external verification (NRC) activities, e Appropriate training was completed.
. Procedure updates identified in the modification package were completed.
Status As of February 5,1997, the work associated with this modification is completed. The associated documents are being reviewed in the Work Control Center. No concerns were identified during the conduct of this work.
This is scheduled to be completed (accepted) by February 7,1997.
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Point Beach Nuclear Plant Unit 2 Restart Commitment Summary (February 5,1997) l Commitment ID#: 43 Commitment
Description:
The following modification will be in an accepted status (i.e., the applicable physical work completed, post-maintenance and return to service testing completed satisfactorily, and the associated component / system being declared operable) prior to being required to be operable per Technical Specifications:
Modification 94-066*A - install a soft seat in containment isolation valve 2SI-834D, and add a relief valve and pressure regulator in the nitrogen supply line to the Si accumulators.
The soft seat is being installed to improve leakage performance. The relief valve and pressure regulator are being installed to ensure the piping is not overpressurized. This resolves a workaround issue.
Completion Timine: This should be in an accepted status prior to Unit 2 leaving cold shutdown.
Criteria to Closcout This Item:
- 1. The modification is in an accepted status.
- 2. The Responsible Person has forwarded the following documentation to the Restart Issues Coordinator:
. A copy of the Installation Work Package page which shows the Duty Shift Supervisor's acceptance of the modification.
- A summary of the significant items / issues identified during conduct of the modification and how they were resolved (can simply reference Condition Report numbers or other tracking mechanisms) OR a statement that there were none identified (report using the NUTRK system - NUTRK U2R22 RESTART Action #
43).
- 3. The Restart Issues Coordinator has verified that the:
. Restart issues File includes the documentation which the Responsible Person is required to forward to the Restart Issues Coordinator (see immediately above).
. Duty Shift Supervisor's signature and date is on the copy of the Installation Work Package page.
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. Significant items / issues identified during conduct of the modification are being tracked in a tracking system which is being reviewed per Restart Commitment #20.
- 4. Completion of an independent verification. This will verify that:
e lhoblems identified or created by the activity are captured.
. The safety evaluation reflects the scope of work completed.
. The scope of work performed reflects the wording of the Restart Commitment. If not, document the rationale for the difference and identify the safety implications.
. Documentation in the Restart File is adequate to support external verification (NRC) activities.
. Appropriate training was completed.
. Procedure updates identified in the modification package were completed.
$tatus:
As of February 5,1997, this is in the closecut verification process.
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i l Point Beach Nuclear Plant Unit 2 Restart Commitment {
i Summary (February 5,1997) l l
Commitment ID#: 44 Commitment
Description:
The following modification will be in an accepted status r (i.e., the applicable physical work completed, post-maintenance and return to service testing completed satisfactorily, and the associated component / system being declared operable) prior to being required to be operable per Technical Specifications:
Modification 96-065 *B - seismically upgrade the Refueling Water Storage Tank recirculation line.
Completion Timine: This should be in an accepted status prior to Unit 2 leaving cold shutdown.
Criteria to Closcout This Item:
- 1. The modification is in an accepted status.
- 2. The Responsible Person has forwarded the fellowing documentation to the Restart ,
Issues Coordinator: ?
. A copy of the Installation Work Package page which shows the Duty Shift Supervisor's acceptance of the modification.
. A summary of the significant items / issues identified during conduct of the modification and how they were resolved (can simply reference Condition Report numbers or other tracking mechanisms) DE a statement that there were none identified (report using the NUTRK system - NUTRK U2R22 RESTART Action #
44).
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- 3. The Restart Issues Coordinator has verified that the-e Restart Issues File includes the documentation which the Responsible Person is required to forward to the Restart issues Coordinator (see immediately above).
. Duty Shift Supervisor's signature and date is on the copy of the Installation Work Package page. l Significant items / issues identified during conduct of the modification are bemg tracked in a tracking system which is being reviewed per Restart Commitment #20.
- 4. Completion of an independent verification. This will verify that:
l
. Problems identified or created by the activity are captured.
l . The safety evaluation reflects the scope of work completed.
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. The scope of work performed reflects the wording of the Restart Commitment. If not, document the rationale for the difference and identify the safety implications.
. Documentation in the Restart File is adequate to support external verification (NRC) activities.
. Appropriate training was completed.
. Procedure updates identified in the modification package were completed.
Status:
As of February 5,1997, this is in progress.
This is scheduled to be completed (accepted) by February 11,1997.
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Point Beach Nuclear Plant Unit 2 Restart Commitment Summary (February 5,1997)
Commitment IDA 45 Commitment
Description:
The following modification will be in an accepted status (i.e., the applicable physical work completed, post-maintenance and return to service testing completed satisfactorily, and the associated component / system being declared operable) prior to being required to be operable per Technical Specifications:
Modification 96-054 - install pressure gauges in the service water return header from the Emergency Diesel Generator GOl and GO2 glycol coolers, and reset the throttle valves in that line.
I GOl and GO2 throttle valves must be reset to meet the assumptions made in the new service water flow model. Prior to the modification, valves were set using an assumed
" worst case" service water return header pressure. The new gauges will allow valves to be set with actual pressure. This will better balance the service water system flows and l enhance service water system performance.
Completion Timine: This should be in an accepted status prior to Unit 2 leaving cold shutdown.
Criteria to Closcout This Item:
- 1. The modification is in an accepted status.
- 2. The Responsible Person has forwarded the following documentation to the Restart issues Coordinator: l l
. A copy of the Installation Work Package page which shows the Duty Shif1 Supervisor's acceptance of the modification.
. A summary of the significant items / issues identified during conduct of the modification and how they were resolved (can simply reference Condition Report numbers or other tracking mechanisms) OR a statement that there were none identified (report using the NUTRK system - NUTRK U2R22 RESTART Action #
45).
- 3. The Restart Issues Coordinator has verified that the:
. Restart Issues File includes the documentation which the Responsible Person is required to forward to the Restart Issues Coordinator (see immediately above).
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e Duty Shift Supervisor's signature and date is on the copy of the Installation Work Package page.
. Significant items / issues identified during conduct of the modification are being tracked in a tracking system which is being reviewed per Restart Commitment #20.
- 4. Completion of an independent verification. This will verify that:
- Problems identified or created by the activity are captured.
. The safety evaluation reflects the scope of work completed.
. The scope of work perfbrmed reflects the wording of the Restart Commitment. If not, document the rationale fbr the difference and identify the safety implications.
- Documentation in the Restart File is adequate to support external verification (NRC) activities.
. Appropriate training was completed.
. Procedure updates identified in the modification package were completed.
S11tinn As of February 4,1997, two outstanding items are delaying work:
. The seismic mounting of gauges will require a new evaluation.
- Concerns due to high flow through the diesel coolers.
These issues will be resolved prior tc initiation of work.
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l Point Beach Nuclear Plant Unit 2 Restart Commitment Summary (February 5,1997) l Cummitment ID#: 46 Commitment
Description:
The following modification will be in an accepted status (i.e., the applicable physical work completed, post-maintenance and return to service testing completed satisfactorily, and the associated component / system being declared operable) prior to being required to be operable per Technical Specifications:
Modification 96-022 - install a new 125 VDC feed (fbr DC Contre! Power) to 480V safeguards bus 2B03. ,
This supports the effbrt to align DC systems which supply DC control power to the 480 V l buses,4160 V buses, and the normally aligned EDGs.
Completion Timine: This should be in an accepted status prior to the Unit 2 core loading. i l
Criteria to Closcout This Item:
- l. The modification is in an accepted status.
- 2. The Responsible Person has forwarded the following documentation to the Restart l Issues Coordinator:
. A copy of the Installation Work Package page which shows the Duty Shift )
Supervisor's acceptance of the modification.
. A summary of the significant items / issues identified during conduct of the modification and how they were resolved (can simply reference Condition Report numbers or other tracking mechanisms) OR a statemer.t that there were none identified (report using the NUTRK system - NUTRK U2R22 RESTART Action #
46).
- 3. The Restart issues Coordinator has verified that the:
- Restart Issues File includes the documentation which the Responsible Person is required to forward to the Restart issues Coordinator (see immediately above).
- Duty Shift Supervisor's signature and date is on the copy of the Installation Work Package page.
- Significant items / issues identified during conduct of the modification are being tracked in a tracking system which is being reviewed per Restart Commitment #20.
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- 4. Completion of an independent verification. This will verify that:
- Problems identified or created by the activity are captured.
- The safety evaluation reflects the scope of work completed.
. The scope of work performed reflects the wording of the Restart Commitment. If not, document the rationale for the difference and identify the safety implications.
. Documentation in the Restart File is adequate to support external verification (NRC) activities.
- Appropriate training was completed.
. Procedure updates identified in the modification package were completed.
Status:
As of February 5,1997 item is in the closecut verification process.
One discrepancy with the test procedure was addressed through Condition Report 96-1153. This issue has been resolved per the Condition Reporting System, and the test procedure was revised to reflect that resolution.
94
1 Point Beach Nuclear Plant Unit 2 Restart Commitment l i
Summary (February 5,1997) l I
l Commitment ID#: 47 l
I Commitment
Description:
The following modification will be in an accepted status I (i.e., the applicable physical work completed, post-maintenance and return to service testing completed satisfactorily, and the associated component / system being declared l operable) prior to being required to be operable per Technical Specifications: l Modification 94-055 - add seismic supports to the raceway between risers 56 and 62 on !
2C04 (Reactor and Primary Plant Control Board).
l The cable tray was sagging due to weakening caused by a sidewall wireway being cut i into the cable tray to allow the exit of some wiring. The addition of these supports restores the full integrity of the cable tray.
Completion Timine: This should be in an accepted status prior to Unit 2 leaving cold shutdown.
Criteria to Closcout This Item:
- 1. The modification is in an accepted status.
)
- 2. The Responsible Person has forwnded the following documentation to the Restart j Issues Coordinator:
- A copy of the Installation Work Package page which shows the Duty Shift Supervisor's acceptance of the modification.
- A summary of the significant items / issues identified during conduct of the modification and how they were resolved (can simply reference Condition Report numbers or other tracking mechanisms) OR a statement that there were none identified (report using the NUTRK system - NUTRK U2R22 RESTART Action #
47).
- 3. The Restart Issues Coordinator has verified that the: j l
e Restart Issues File includes the documentation which the Responsible Person is !
required to forward to the Restart issues Coordinator (see immediately above). !
e Duty Shift Supervisor's signature and date is on the copy of the Installation Work Package page.
- Significant items / issues identified during conduct of the modification are being tracked in a tracking system which is being reviewed per Restart Commitment #20, 1
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- 4. Completion of an independent verification. This will verify that:
- Problems identified or created by the activity are captured.
. The safety evaluation reflects the scope of work completed.
. The scope of work performed reflects the wording of the Restart Commitment. If not, document the rationale for the difference and identify the safety implications.
. Documentation in the Restart File is adequate to support external verification (NRC) activities.
. Appropriate training was completed.
. Procedure updates identified in the modification package were completed.
Status:
As of February 5,1997, this item is in the closeout verification process. There were no safety significant issues or discrepancies associated with either the installation or the testing of this modification.
96
l Point Beach Nudear Plant Unit 2 Restart Commitment -
Summary (February 5,1997) i Commitment ID#: 48 l
l Commitment Descrintion: The following modification will be in an accepted status (i.e., the applicable physical work completed, post-maintenance and return to service testing completed =atisfactorily, and the associated component / system being declared operable) prior to being required to be operable per Technical Specifications: i Modification 96-0688 - eliminate containment heating steam and condensate return containment isolation valves.
These were determined to be unnecessary to support plant operations. Removal eliminates a potential containment leakage path and reduces the need to conduct future Appendix J testing on these.
Completion Timing: This should be in an accepted status prior to Unit 2 leaving cold shutdown.
Criteria to Closcout This Item:
- 1. The modification is in an accepted status.
l
- 2. The Responsible Person has forwarded the following documentation to the Restart Issues Coordinator:
. A copy of the Installation Work Package page which shows the Duty Shift Supervisor's acceptance of the modification. i e A summary of the significant items / issues identified during conduct of the modification and how they were resolved (can simply reference. Condition Report numbers or other tracking mechanisms) DR a statement that there were none i identified (report using the NUTRK system - NUTRK U2R22 RESTART Action #
48).
- 3. The Restart Issues Coordinator has verified that the:
- Restart Issues File includes the documentation which the Responsible Person is required to forward to the Restart Issues Coordinator (see immediately above).
- Duty Shift Supervisor's signature and date is on the copy of the Installation Work l Package page.
- Significant items / issues identified during conduct of the modification are being tracked in a tracking system which is being reviewed per Restart Commitment #20.
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- 4. Completion of an independent verification. This will verify that:
. Problems identified or created by the activity are captured.
e The safety evaluation re'lects the scepe of work completed.
- The scope of work perforcned reflect; the wording of the Restart Commitment. If not, document the rationale for the afference and identify the safety implications.
- Documentation in the Restart File is adequate to support external verification (NRC) activities.
. Appropriate training was completed.
- Procedure updates identified in the modification package were completed.
Status:
As of February 5,1997, this is in progress.
This is scheduled to be completed (accepted) by February 18,1997.
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Point Beach Nuclear Plant Unit 2 Restart Commitment Summary (February 5,1997)
P Commitment ID#: 49 Commitment
Description:
The following modification will be in an accepted status (i.e., the applicable physical work completed, post-maintenance testing and return to service completed satisfactorily, and the associated component / system being declared operable) prior to being required to be operable per Technical Specifications:
Modification 96-053 - replace an elbow in the west service water header.
A temporary, non-code repair was performed in July 1996 on the service water 6 inch ;
elbow per temporary modification TM 96-014. There is an NRC commitment to perfonn the code repair prior to the exit from the next refueling outage. Funher pipe inspections ,
revealed a second elbow with wall thinning (no leak yet). Both elbows are normally I unisolable from the west service water header.
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Completion Timine: This should be in an accepted status prior to Unit 2 leaving cold shutdown. i l
Criteria to Closcout This Item: '
- l. The modification is in an accepted status.
- 2. The Responsible Person has forwarded the following documentation to the Restart Issues Coordinator:
. A copy of the Installation Work Package page which shows the Duty Shift Supervisor's acceptance of the modification.
. A summary of the significant items / issues identified during conduct of the modification and how they were resolved (can simply reference Condition Report numbers or other tracking mechanisms) DR a statement that there were none identified (report using the NUTRK system - NUTRK U2R22 RESTART Action #
49).
- 3. The Restart Issues Coordinator has verified that the:
- Restart Issues File includes the documentation which the Responsible Person is required to forward to the Restart issues Coordinator (see immediately above).
. Duty Shift Supervisor's signature and date is on the copy of the Installation Work Package page.
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e Significant items / issues identified during conduct of the modification are being tracked in a tracking system which is being reviewed per Restart Commitment #20.
- 4. Completion of an independent verification. This will verify that:
. Problems identified or created by the activity are captured.
. The safety evaluation reflects the scope of work completed.
. The scope of work performed reflects the wording of the Restart Commitment. If not, document the rationale for the difference and identify the safety implications.
- Documentation in the Restart File is adequate to support external verification (NRC) activities.
- Appropriate training was completed.
. Procedure updates identified in the modification package were completed.
Status:
As of Febmary 5,1997, the installation is scheduled for February 8-12,1997.
The scheduled completion (acceptance) date is February 13,1997.
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l Point Beach Nuclear Plant Unit 2 Restart Commitment
! Summary (February 5,1997)
Commitment ID#: 50 l Commitment
Description:
The following modification will be in an accepted status 1 l (i.e., the applicable physical work completed, post-maintenance and return to service !
testing completed satisfactorily, and the associated component / system being declared operable) prior to being required to be operable per Technical Specifications:
Modification 95-070 - seismically upgrade the containment cooling fans and filters. 1 Completion Timine: This should be in an accepted status prior to Unit 2 leaving cold shutdown. l 1
Criteria to Closcout This Item:
- 1. The modification is in an accepted status.
- 2. The Responsible Person has forwarded the following documentation to the Restart issues Coordinator:
. A copy of the Installation Work Package page which shows the Duty Shift Supervisor's acceptance of the modification. ;
e A summary of the significant items / issues identified during conduct of the modification and how they were resolved (can simply reference Condition Report numbers or other tracking mechanisms) DE a statement that there were none identified (report using the NUTRK system - NUTRK U2R22 RESTART Action #
50).
- 3. The Restart Issues Coordinator has verified that the:
- Restart issues File includes the documentation which the Responsible Person is required to forward to the Restart Issues Coordinator (see immediately above).
- Duty Shift Supervisor's signature and date is on the copy of the Installation Work Package page.
. Significant items / issues identified during conduct of the modification are being tracked in a tracking system which is being reviewed per Restart Commitment #20. ,
- 4. Completion of an independent verification. This will verify that: l
. Problems identified or created by the activity are captured. l
- The safety evaluation reflects the scope of work completed.
101 I
e The scope of work performed reflects the wording of the Restart Commitment. If not, document the rationale for the difference and identify the safety implications.
- Documentation in the Restart File is adequate to support external verification (NRC) activities.
. Appropriate training was completed.
. Procedure updates identified in the modification package were completed.
Status:
As of February 5,1997, this is in progress l
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Point Beach Nuclear Plant Unit 2 Restart Commitment Summary (February 5,1997)
Commitment ID#: 51 Commitment
Description:
The following modification will be in an accepted status (i.e., the applicable physical work completed, post-maintenance and return to service l testing completed satisfactorily, and the associated component / system being declared ;
operable) prior to being required to be operable per Technical Specifications:
Modification 96-026 -install, delete, and modify supports for feedwater, main steam, and Si system piping for the 79-14 project.
The piping and pipe supports for these systems have been evaluated for their ability to withstand design basis loads and stresses. Analysis shows that these piping systems are operable in their present configuration and prior to these modifications. However, various transients have been postulated that could result in stresses above code allowances, and these modifications will reduce these stresses to below code allowable.
Completion Timine: This should be in an accepted status prior to Unit 2 leaving cold i shutdown. l Criteria to Closcout This Item:
- 1. The modification is in an accepted status.
- 2. The Responsible Person has forwarded the following documentation to the Restart Issues Coordinator:
- A copy of the Installation Work Package page which shows the Duty Shift Supervisor's acceptance of the modification.
- A summary of the significant items / issues identified during conduct of the modification and how they were resolved (can simply reference Condition Report numbers or other tracking mechanisms) .QR a statement that there were none identified (report using the NUTRK system - NUTRK U2R22 RESTART Action #
51).
- 3. The Restart Issues Coordinator has verified that the:
- Restart Issues File includes the documentation which the Responsible Person is required to forward to the Restart Issues Coordinator (see immediately above).
. Duty Shift Supervisor's signature and date is on the copy of the Installation Work Package page.
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i e Significant items / issues identified during conduct of the modification are being tracked in a tracking system which is being reviewed per Restart Commitment #20.
1
- 4. Completion of an independent verification. This will verify that:
l
- Problems identified or created by the activity are captured.
- The safety evaluation reflects the scope of work completed.
- The scope of work performed reflects the wording of the Restart Commitment. If not, document the rationale for the difference and identify the safety implications.
- Documentation in the Restart File is adequate to support external verification (NRC) activities.
- Appropriate training was completed.
- Procedure updates identified in the modification package were completed.
SLttusi As of February 5,1997, this item is in the closeout verification process.
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l Point Beach Nuclear Plant Unit 2 Restart Commitment i Summary (February 5,1997)
Commitment ID#: 52 l Commitment
Description:
The following modification will be in an accepted status (i.e., the applicable physical work completed, post-maintenance and return to service testing completed satisfactorily, and the associated component / system being declared operable) prior to being required to be operable per Technical Specifications:
Modification 96-058 - move Power Plant Computer System alarms to the exterior of C-20 panels. This will enhance the alarm sound levels.
Completion Timing: This should be in an accepted status prior to Unit 2 leaving cold shutdown.
Criteria to Clonnut This Item:
- 1. The modification is in an accepted status.
- 2. The Responsible Person has forwarded the following documentation to the Restart Issues Coordinator:
- A copy of the Installation Work Package page which shows the Duty Shift Supervisor's acceptance of the modification. i e A summary of the significant items / issues identified during conduct of the modification and how they were resolved (can simply reference Condition Report numbers or other tracking mechanisms) OR a statement that there were none identified (report using the NUTRK system - NUTRK U2R22 RESTART Action # 1 52)
- 3. The Restart Issues Coordinator has verified that the:
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- Restart Issues File inch'aes the documentation which the Responsible Person is required to forward to .he Restart Issues Coordinator (see immediately above).
. Duty Shift Supervisor's signature and date is on the copy of the Installation Work )
Package page.
- Significant items / issues identified during conduct of the modification are being tracked in a tracking system which is being reviewed per Restart Commitment #20.
- 4. Completion of an independent verification. This will verify that:
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- Problems identified or created by the activity are captured.
l 105 l l
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. The safety evaluation reflects the scope of work completed.
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. The scope of work performed reflects the wording of the Restart Commitment. If I l
l not, document the rationale for the difTerence and identify the sr?ety implications.
l . Documentation in the Restart File is adequate to support externas verubation (NRC) activities. l
. Appropriate training was completed.
. Procedure updates identified in the modification package were completed.
Status:
As of February 5,1997, this item is in the closecut verification process. No issues were identified during the conduct of the modification.
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Point Beach Nuclear Plant Unit 2 Restart Commitment l Summary (February 5,1997) I I
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1 Commitment ID#: 53 Commitment
Description:
The following modification will be in an accepted status (i.e., the applicable physical work completed, post-maintenance and return to service testing completed satisfactorily, and the associated component / system being declared operable) prior to being required to be operable per Technical Specifications:
Modification 94-095 - replace 8 Main Steam Condenser steam dump valves with ;
improved design.
l This will resolve a workaround issue, as the performance of these valves has not been satisfactory. l 1
l Completion Timine: This should be in an accepted status prior to Unit 2 leaving cold shutdown.
l Criteria to Closcout This Item:
l
- 1. The modification is in an accepted status. l l
- 2. The Responsible Person has forwarded the following documentation to the Restart Issues Coordinator:
. A copy of the Installation Work Package page which shows the Duty Shift Supervisor's acceptance of the modiHcation, e A summary of the signiHeant items / issues identified during conduct of the modification and how they were resolved (can simply reference Condition Report numbers or other tracking mechanisms) OR a statement that there were none identified (report using the NUTRK system - NUTRK U2R22 RESTART Action #
53).
- 3. The Restart Issues Coordinator has verified that the:
- Restart Issues File includes the documentation which the Responsible Person is I required to forward to the Restart issues Coordinator (see immediately above). I l
- Duty Shift Supervisor's signature and date is on the copy of the Installation Work l Package page.
e Significant items / issues identified during conduct of the modification are being l
tracked in a tracking system which is being reviewed per Restart Commitment #20.
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1
- 4. Completion of an independent verification. This will verify that:
l . Problems identified or created by the activity are captured.
. The safety evaluation reflects the scope of work completed.
. The scope of work performed reflects the wording of the Restart Commitment. If not, document the rationale for the difference and identify the safety implications.
Documentation in the Restart File is adequate to support extemal verifi, cation (NRC) activities. 1
. Appropriate training was completed.
. Procedure updates identified in the modification package were completed. j l
Status: j As of January 29,1997, the physical work is in progress.
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Point Beach Nuclear Plant Unit 2 Restart Commitment Summary (February 5,1997)
Commitment ID#: 54 Commitment
Description:
The following modification will be in an accepted status (i.e., the applicable physical work completed, post-maintenance and return to service testing completed satisfactorily, and the associated component / system being declared operable) prior to being required to be operable per Technical Specifications:
Modification 95-029 - replace SI accumulator level transmitters.
The pmpose of this modification is to provide a more accurate and reliable level indication system for the Si accumulators. The cunent capacitance probe type level indicators are being replaced with Rosemount differential pressure transmitters.
Completion Timine: This should be in an accepted status prior to Unit 2 leaving cold shutdown. j Criteria to Closcout This Item:
- 1. The modification is in an accepted status.
- 2. The Responsible Person has forwarded the following documentation to the Restart Issues Coordinator-I
- A copy of the Installation Work Package page which shows the Duty Shift Supervisor's acceptance of the modification.
. A summary of the significant items / issues identified during conduct of the !
I modification and how they were resolved (can simply reference Condition Report numbers or other tracking mechanisms) OR a statement that there were none l identified (report using the NUTRK system - NUTRK U2R22 RESTART Action # l 54).
- 3. The Restart Issues Coordinator has verified that the:
. Restart Issues File includes the documentation which the Responsible Person is required to forward to the Restart Issues Coordinator (see immediately above).
. Duty Shift Supervisor's signature and date is on the copy of the Installation Work !
Package page. !
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- Significant items / issues identified during conduct of the modification are being tracked in a tracking system which is being reviewed per Restart Commitment #20.
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- 4. Completion of an independent verification. This will verify that:
. Problems identified or created by the activity are captured.
. The safety evaluation reflects the scope of work completed.
. The scope of work performed reflects the wording of the Restart Commitment. If not, document the rationale for the difference and identify the safety implications.
. Documentation in the Restart File is adequate to support external verification (NRC) activities. l
. Appropriate training was completed.
. Procedure updates identified in the modification package were completed.
Status:
As of February 5,1997, this is waiting for completion of PMT. The remaining testing includes a leak test and functional testing, both of which cannot be done until the accumulators are restored, which is presently scheduled for after the Integrated Leak Rate Test (ILRT).
The scheduled completion (acceptance) date is February 24,1997.
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Point Beach Nuclear Plant Unit 2 Restart Commitment Summary (February 5,1997)
Commitment ID#: 55 Commitment
Description:
The following modification will be in an accepted status (i.e., the applicable physical work completed, post-maintenance and return to service testing completed satisfactorily, and the associated component / system being declared operable) prior to being required to be operable per Technical Specifications:
Modification 95-035 - modify Containment Spray additive tank controller circuit.
Completion Timing: This should be in an accepted status prior to Unit 2 leaving cold shutdown.
Criteria to Closcout This Item:
- 1. The modification is in an accepted status.
- 2. The Responsible Person has forwarded the following documentation to the Restart Issues Coordinator: !
- A copy of the Installation Work Package page which shows the Duty Shift Supervisor's acceptance of the modification.
. A summary of the significant items / issues identified during conduct of the modification and how they were resolved (can simply reference Condition Report numbers or other tracking mechanisms) OR a statement that there were none identified (report using the NUTRK system - NUTRK U2R22 RESTART Action #
55).
- 3. The Restart Issues Coordinator has verified that the: ;
e Restart issues File includes the documentation which the Responsible Person is required to forward to the Restart Issues Coordinator (see immediately above).
- Duty Shift Supervisor's signature and date is on the copy of the Installation Work Package page.
- Significant items / issues identified during conduct of the modification are being tracked in a tracking system which is being reviewed per Restart Commitment #20.
l 4. Completion of an independent verification. This will verify that:
. Problems identified or created by the activity are captured.
( . The safety evaluation reflects the scope of work completed.
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. The scope of work performed reflects the wording of the Restart Commitment. If not, document the rationale for the difference and identify the safety implications.
. Documentation in the Restart File is adequate to support external verification
('NRC) activities.
. Appropriate training was completed.
. Procedure updates identified in the modification package were completed.
Status:
As of February 5,1997, this item is in the closcout verification process. A controller was identified as defective during conduct of the modification and was replaced.
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1 Point Beach Nuclear Plant Unit 2 Restart Commitment Summary (February 5,1997) I i
Commitment ID#: 56 Commitment
Description:
The following modification will be in an accepted status j (i.e., the applicable physical work completed, post-maintenance and return to service l testing completed satisfactorily, and the associated component / system being declared operable) prior to being required to be operable per Technical Specifications: i Modification 96-063 - replace 345 kv breakers (3-4,4-5, and 142).
During extremely cold winter conditions, these switchyard breakers experienced air loss, making them difficult to operate. This replacement will ensure their operability during these conditions.
Completion Timine: The physical work associated with this modification should be completed prior to criticality. To conduct the PMT (which involves relaying checks), the !
unit must be on-line. l Criteria to Closcout This Item:
- 1. The modification is in an accepted status.
I
- 2. The Responsible Person has forwarded the following documentation to the Restart l Issues Coordinator: I e A copy of the Installation Work Package page which shows the Duty Shift Supervisor's acceptance of the modification.
. A summary of the significant items / issues identified during conduct of the modification and how they were resolved (can simply reference Condition Report numbers or other tracking mechanisms) OR a statement that there were none identified (report using the NUTRK system - NUTRK U2R22 RESTART Action #
56). .
- 3. The Restart Issues Coordinator has verified that the:
- Restart Issues File includes the documentation which the Responsible Person is required to forward to the Restart Issues Coordinator (see immediately above).
- Duty Shift Supervisor's signature and date is on the copy of the Installation Work Package page.
. Significant items / issues identified during conduct of the modification are being tracked in a tracking system which is being reviewed per Restart Commitment #20.
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- 4. Completion of an independent verification. This will verify that:
- Problems identified or created by the activity are captured.
. The safety evaluation reflects the scope of work completed.
. The scope of work performed reflects the wording of the Restart Commitment. If not, document the rationale for the difference and identify the safety implications.
. Documentation in the Restart File is adequate to support external verification (NRC) activities.
- Appropriate training was completed.
- Procedure updates identified in the modification package were completed.
Status:
As of February 5,1997, the physical work is completed, and the modification is awaiting PMT. To conduct the PMT (which involves relaying checks with the generator breaker closed and energized), the unit must be on-line. A procedure update to PC-21 must also be made to allow acceptance of this modification.
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Point Beach Nuclear Plant Unit 2 Restart Commitment Summary (February 5,1997) l l
l Commitment ID#: 57 .
Commitment
Description:
The following modification will be in an accepted status (i.e., the applicable physical work completed, post-maintenance and return to service testing completed satisfactorily, and the associated component / system being declared !
operable) prior to being required to be operable per Technical Specifications: j Modification 96-069 - replace four breakers (1 Y-06-01,1 Y-06-03,1 Y-06-05, and 1 Y l
- 11) associated with instrument bus 1 Y-06.
l This will resolve an issue where these breakers are oversized for the wiring they are protecting, creating a potential delay or lack of breaker tripping situation should a fault occur.
Completion Timine: This should be in an accepted status prior to Unit 2 leaving cold shutdown.
Criteria to Closcout This Item:
- 1. The modification is in an accepted status. I
- 2. The Responsible Person has forwarded the following documentation to the Restart Issues Coordinator: l
- A copy of the Installation Work Package page which shows the Duty Shift Supervisor's acceptance of the modification.
. A summary of the significant items / issues identified during conduct of the modification and how they were resolved (can simply reference Condition Report numbers or other tracking mechanisms) 2 a statement that there were none identified (report using the NUTRK system - NUTRK U2R22 RESTART Action #
57).
- 3. The Restart Issues Coordinator has verified that the:
. Restart Issues File includes the documentation which the Responsible Person is required to forward to the Restart Issues Coordinator (see immediately above).
. Duty Shift Supervisor's signature and date is on the copy of the Installation Work Package page.
. Significant items / issues identified during conduct of the modification are being l tracked in a tracking system which is being reviewed per Restart Commitment #20.
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- 4. Completion of an independent verification. This will verify that:
. Problems identified or created by the activity are captured.
l
. The safety evaluation reflects the scope of work completed.
j . The scope of work performed reflects the wording of the Restart Commitment. If l not, document the rationale for the difference and identify the safety implications.
l
. Documentation in the Restart File is adequate to support external verification l (NRC) activities.
l . Appropriate training was completed.
. Procedure updates identified in the modification package were completed.
Status:
i As of February 5,1997, the work associated with this modification is scheduled fbr the )
last week of February. The work orders have been written, and parts are on-site. A 50.59 evaluation, the modification package, and work plans need to be prepared.
1 The scheduled completion (acceptance) date is March 3,1997. l l
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Point Beach Nuclear Plant Unit 2 Restart Commitment Summary (February 5,1997)
Commitment ID#: 58 Commitment Descriptio1n The following modification will be in an accepted status (i.e., the applicable physical work completed, post-maintenance and retum to service i testing completed satisfactorily, and the associated component / system being declared operable) prior to being required to be operable per Technical Specifications:
Modification 95-058*O - repair Steam Generator intermediate leg supports. These were found degraded, and this issue may be resolved through analysis.
l Completion Timine: This should be in an accepted status prior to the Unit 2 core loading.
Criteria to Closcout This Item:
- 1. The modification is in an accepted status.
- 2. The Responsible Person has forwarded the following documentation to the Restart Issues Coordinator:
I
. A copy of the Installation Work Package page which shows the Duty Shift '
Supervisor's acceptance of the modification. .
. A summary of the significant items / issues identified during conduct of the !
modification and how they were resolved (can simply reference Condition Report numbers or other tracking mechanisms) OR a statement that there were none identified (report using the NUTRK system - NUTRK U2R22 RESTART Action #
58). j i
- 3. The Restart Issues Coordinator has verified that the:
. Restart Issues File includes the documentation which the Responsible Person is I i required to forward to the Restart issues Coordinator (see immediately above).
- Duty Shift Supervisor's signature and date is on the copy of the Installation Work Package page.
. Significant items / issues identified during conduct of the modification are being tracked in a tracking system which is being reviewed per Restart Commitment #20.
1
- 4. Completion of an independent verification. This will verify that:
i e Problems identified or created by the activity are captured.
. The safety evaluation reflects the scope of work completed.
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. The scope of work performed reflects the wording of the Restart Commitment. If not, document the rationale for the difference and identify the safety implications.
. Documentation in the Restart File is adequate to support external verification (NRC) activities.
- Appropriate training was completed.
- Procedure updates identified in the modification package were completed.
Status:
As of February 5,1997, this item is in the closecut verification process.
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Point Beach Nuclear Plant Unit 2 Restart Commitment Summary (February 5,1997)
Commitment ID#: 59 Commitment
Description:
The following modification will be in an accepted status (i.e., the applicable physical work completed, post-maintenance and return to service testing completed satisfactorily, and the associated component / system being declared operable) prior to being required to be operable per Technical Specifications:
Modification 96-070 - replace molded case circuit breakers associated with instrument buses 2Y-05 and 2Y-06.
This will resolve an issue where these breakers are oversized for the wiring they are protecting, creating a potential delay or lack of breaker tripping situation should a fault occur.
Completion Timine: This should be in an accepted status prior to Unit 2 leaving cold shutdown.
Criteria to Closcout This Item:
- 1. The modification is in an accepted status, i
- 2. The Responsible Person has forwarded the following documentation to the Restart Issues Coordinator:
I
- A copy of the Installation Work Package page which shows the Duty Shift l Supervisor's acceptance of the modification. l I
- A summary of the significant items / issues identified during conduct of the modification and how they were resolved (can simply reference Condition Report numbers or other tracking mechanisms) OR a statement that there were none identified (report using the NUTRK system - NUTRK U2R22 RESTART Action #
59).
- 3. The Restart Issues Coordinator has verified that the:
- Restart Issues File includes the documentation which the Responsible Person is required to forward to the Restart Issues Coordinator (see immediately above). l
- Duty Shift Supervisor's signature and date is on the copy of the Installation Work )
Package page. l
- Significant items / issues identified during conduct of the modification are being I tracked in a tracking system which is being reviewed per Restart Commitment #20.
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- 4. Completion of an independent verification. This will verify that:
l
. Problems identified or created by the activity are captured.
l
. The safety evaluation reflects the scope of work completed.
. The scope of work performed reflects the wording of the Restart Commitment. If l not, document the rationale for the difference and identify the safety implications.
l
. Documentation in the Restart File is adequate to support external verification
! (NRC) activities.
! . Appropriate training was completed.
. Procedure updates identified in the modification package were completed.
Status:
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As of February 5,1997, the physical work and PMT have been completed. The modification paperwork is in the process of closeout.
This is scheduled to be completed (accepted) by February 8,1997.
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Point Beach Nuclear Plant Unit 2 Restart Commitment Summary (February 5,1997)
Commitment ID#: 60 Commitment
Description:
_ The work and testing associated with these work orders will be completed prior to the associated component / system being declared operable: Work l Orders 9601506,9602502,9603921,9611267,9611278, and 9611755 - replace proximity switches and targets with an improved design and overhaul the Fuel Transfer j Cart to enhance control system operation.
l l The original equipment manufacturer had provided switches not designed for underwater service, causing a history of recurring failures. This will resolve a workaround issue.
Completion Timine: This should be completed prior to the Unit 2 core loading.
l
_ Criteria to Closcout This Item:
- 1. Completion of the work associated with the listed work orders.
- 2. The Responsible Person has forwarded the following documentation to the Restart Issues Coordinator:
- A copy of page 2 from the closed work orders (the Duty Shift Supervisor's signature and date in the " Equipment Return to Service" section indicates that the associated equipment is operable).
. A summary of the significant items / issues identified during conduct of the work orders and how they were resolved (can simply reference Condition Report numbers or other tracking mechanisms) OR a statement that there were none identified (report using the NUTRK system - NUTRK U2R22 RESTART Action
- 60).
- 3. The Restart Issues Coordinator has verified that the:
- Restart Issues File includes the documentation which the Responsible Person is required to forward to the Restart Issues Coordinator (see immediately above).
- Duty Shift Supervisor's signature and date is on the " Equipment Return to Service" section on page 2 of the associated work orders.
- Significant items / issues identified during conduct of the work orders are being tracked in a tracking system which is being reviewed per Restart Commitment #20.
l 121 i l
- 4. Completion of an independent verification. This will verify that:
. Problems identified or created by the activity are captured.
. The scope of work perfonned refbets the wording of the Restart Commitment. !r not, document the rationale for the difference and identify the safety implications.
. Documentation in the Restart File is adequate to support external verification (NRC) activities.
. Appropriate training was completed.
Status:
As of February 5,1997, this is in closeout verification.
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Point Beach Nuclear Plant Unit 2 Restart Commitment Summary (February 5,1997) '
Commitment ID#: 61 Commitment
Description:
The work and testing associated with these work orders will be completed prior to the associated component / system being declared operable: Work Orders 9613568 and 9613569 - provide bonnet pressure locking relief for the Sl-857A and SI-857Il valves (interface valves between RHR and High Head SI) on Unit 2. These are critical, manually operated valves.
Completion Timine: This should be completed prior to the Unit 2 core loading.
l
! Criteria to Closcout This Item:
l l 1. Completion of the work associated with the listed work orders.
l 2. The Responsible Person has forwarded the following documentation to the Restart l Issues Coordinator:
. A copy of page 2 from the closed work orders (the Duty Shift Supervisor's !
signature and date in the " Equipment Return to Service" section indicates that the 1 1
l associated equipment is operable).
l . A summary of the significant items / issues identified during conduct of the work l orders and how they were resolved (can simply reference Condition Report j numbers or other tracking mechanisms) M a statement that there were none identified (report using the NUTRK system - NUTRK U2R22 RESTART Action
- 61).
- 3. The Restart Issues Coordinator has verified that the: I
- Restart Issues File includes the documentation which the Responsible Person is required to forward to the Restart Issues Coordinator (see immediately above).
. Duty Shift Supervisor's signature and date is on the " Equipment Return to l Service" section on page 2 of the associated work orders.
l . Significant items / issues identified during conduct of the work orders are being tracked in a tracking system which is being reviewed per Restart Commitment #20.
- 4. Completion of an independent verification. This will verify that:
. Problems identified or created by the activity are captured.
. The scope of work performed reflects the wording of the Restart Commitment. If not, document the rationale for the difference and identify the safety implications.
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e Documentation in the Restart File is adequate to support external verification (NRC) activities.
. Appropriate training was completed.
Status:
As of February 5,1997, the physical work has been completed, and the activity is in the PMT phase. Procedure changes must also be completed for this to be considered complete.
The scheduled completion date is February 10,1997.
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l Point Beach Nuclear Plant Unit 2 Restart Commitment -
Summary (February 5,1997)
Commitment ID#: 62 Commitment
Description:
The work and testing associated with this work order will be completed prior to the associated component / system being declared operable: Work l Order 9611757 - correct the leakage which leads to boric acid buildup in the cylinder blocks of"B" Charging Pump. !
, l This is a housekeeping issue, not an operability issue. Resolution will bring this into compliance with Maintenance Department housekeeping standards.
Completion Timine: This should be completed prior to Unit 2 leaving cold shutdown.
Criteria to Closcout This Item:
- 1. Completion of the work associated with the listed work order.
- 2. The Responsible Person has forwarded the following documentation to the Restart 3 issues Coordinator: '
. A copy of page 2 from the closed work order (the Duty Shift Supervisor's signature and date in the " Equipment Return to Service" section indicates that the j associated equipment is operable). l
- A summary of the significant items / issues identified during conduct of the work !
order and how they were resolved (can simply reference Condition Report numbers or other tracking mechanisms) OR a statement that there were none identified (report using the NUTRK system - NUTRK U2R22 RESTART Action #62). I
- 3. The Restart Issues Coordinator has verified that the:
- Restart issues File includes the documentation which the Responsible Person is required to forward to the Restart Issues Coordinator (see immediately above).
- Duty Shift Supervisor's signature and date is on the " Equipment Return to Service" section on page 2 of the associated work order. l e Significant items / issues identified during conduct of the work order are bemg tracked in a tracking system which is being reviewed per Restart Commitment #20.
- 4. Completion of an independent verification. This will verify that:
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- Problems identified or created by the activity are captured.
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. The scope of work performed reflects the wording of the Restart Commitment. If not, document the rationale for the difference and identify the safety implications.
- Documentation in the Restart File is adequate to support external verification (NRC) activities.
- Appropriate training was completed.
Status:
As of February 5,1997, the physical work associated with this work order has been completed, and it is awaiting PMT.
The scheduled completion date is February 20,1997.
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Point Beach Nuclear Plant Unit 2 Restart Commitment Summary (February 5,1997)
Commitment ID#: 63 Commitment
Description:
The work and testing associated with this work order will be campleted prior to the associated component / system being declared operable: Work Order 9603532 - repair the handswitch for 2P-2A, the "A" Charging Pump.
This handswitch has a history of not operating smoothly, and this was addressed in the past through the use oflubricants. A change in maintenance philosophy prompted the replacement of this component.
Completion Timine: This should be completed prior to Unit 2 leaving cold shutdowr..
Criteria to Closcout This Itemt
- 1. Completion of the work associated with the listed work order. L
- 2. The Responsible Person has forwarded the following documentation to the Restart issues Coordinator:
. A copy of page 2 from the closed work order (the Duty Shift Supervisor's signature and date in the " Equipment Return to Service" section indicates that the associated equipment is operable).
. A summary of the significant items / issues identified during conduct of the work ,
order and how they were resolved (can simply reference Condition Report numbers I or other tracking mechanisms) OR a statement that there were none identified (report using the NUTRK system - NUTRK U2R22 RESTART Action #63). 1 l
l
- 3. The Restart Issues Coordinator has verified that the:
. Restart issues File includes the documentation which the Responsible Person is required to forward to the Restart Issues Coordinator (see immediately above).
. Duty Shift Supervisor's signature and date is on the " Equipment Return to Service" section on page 2 of the associated work order.
. Significant items / issues identified during conduct of the work order are being tracked in a tracking system which is being reviewed per Restart Commitment #20.
- 4. Completion of an independent verification. This will verify that:
. Problems identified or created by the activity are captured.
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. The scope of work performed reflects the wording of the Restart Commitment. If not, document the rationale for the difference and identify the safety implications.
. Documentation in the Restart File ir adequate to support external verification (NRC) activities.
. Appropriate training was completed.
Status:
As of January 28,1997, the physical work is complete, and the work order is awaiting PMT.
The scheduled completion date is February 20,1997.
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Point Beach Nuclear Plant Unit 2 Restart Commitment Summary (February 5,1997)
Commitment ID#: 64 Commitment
Description:
The work and testing associated with these work orders will be completed prior to the associated component / system being declared operable: Work Orders 9611624 through 9611626 - replace existing pneumatic turbine generator circuitry time delay relays with plug-in, electronic time delay relays.
The ease of calibration and cycle drift will be improved through this change.
Completion Timingt This should be completed prior to Unit 2 leaving cold shutdown.
Criteria to Closcout This Item:
- 1. Completion of the work associated with the listed work orders.
- 2. The Responsible Person has forwarded the following documentation to the Restart Issues Coordinator:
- A copy of page 2 from the closed work orders (the Duty Shift Supervisor's signature and date in the " Equipment Return to Service" section indicates that tiie associated equipment is operable).
- A summary of the signi6 cant items / issues identi6ed during conduct of the work orders and how they were resolved (can simply reference Condition Report numbers or other tracking mechanisms) OR a statement that there were none identined (report using the NUTRK system - NUTRK U2R22 RESTART Action
- 64).
- 3. The Restart Issues Coordinator has verified that the: ;
e Restart Issues File includes the documentation which the Responsible Person is required to forward to the Restart Issues Coordinator (see immediately above). j e Duty Shift Supervisor's signature and date is on the " Equipment Return to i Service" section on page 2 of the associated work orders. l
- Significant items / issues identified during conduct of the work orders are being l tracked in a tracking system which is being reviewed per Restart Commitment #20.
- 4. Completion of an independent verification. This will v:rify that:
- Problems identified or created by the activity are captured. l 1
l 129
e The scope of work performed reflects the wording of the Restart Commitment. If not, document the rationale for the difference and identify the safety implications.
- Documentation in the Restart File is adequate to support external verification (NRC) activities.
. Appropriate training was completed.
Status:
As of February 5,1997, the work plans have been prepared, and the work order is scheduled.
The scheduled completion date is February 24,1997.
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l Point Beach Nuclear Plant Unit 2 Restart Commitment i Summary (February 5,1997) !
Commitment ID#: 65 l Commitment
Description:
The work and testing associated with this work order will be completed prior to the associated component / system being declared operable: Work l l '
Order 9606626 - reinstall switches on the Unit 2 Containment hatch third door to allow monitoring of door status.
There have been recurring human performance errors associated with this door, as people would block it open during refueling operations to transfer equipment. To ensure the operability of this door, switches are being installed to allow remote monitoring ofits status.
Completion Timine: This should be completed prior to the Unit 2 core loading.
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Criteria to Closcout This Item:
- 1. Completion of the work associated with the listed work order.
- 2. The Responsible Person has forwarded the following documentation to the Restert Issues Coordinator:
I e A copy of page 2 from the closed work order (the Duty Shift Supervisor's signature and date in the " Equipment Return to Service" section indicates that the associated equipment is operable).
- A summary of the signincant items / issues identined during conduct of the work order and how they were resolved (can simply reference Condition Report numbers or other trackir.g mechanisms) OR a statement that there were none identined (report using the NUTRK system - NUTRK U2R22 RESTART Action #65).
- 3. The Restart Issues Coordinator has veriGed that the:
. Restart Issues File includes the documentation which the Responsible Person is required to forward to the Restart Issues Coordinator (see immediately above).
. Duty Shift Supervisor's signature and date is on the " Equipment Return to Service" section on page 2 of the associated work order.
. Signincant items / issues identined during conduct of the work order are being tracked in a tracking system which is being reviewed per Restart Commitment #20.
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_. _ ._ _ . _ . . . _ . . . _ _ . _ . . ~ _ _ . . _ . . . _ . . _ . . . . - . . _ _ - _ . _ _ . _ . _ . . _ . _ . _ . _ . _ .
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- 4. Completion of an independent verification. This will verify that:
.i e - Problems identified or created by the activity are captured. l e The scope of work performed reflects the wording of the Restart Commitment. If ;
l l
not, document the rationale for the difference and identify the safety implications.- j e Documentation in the Restart File is adequate to support external verification )
(NRC) activities. i e Appropriate training was completed.
f Status: '
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As of February 5,1997, the work is complete, and this is in the closecut verification [
l_ process.
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i Point Beach Nuclear Plant Unit 2 Restart Commitment Summary (February 5,1997)
Commitment ID#: 66 l
! Commitment
Description:
The work and testing associated with this work order will be completed prior to the associated component / system being declared operable: Work Order 9611052 - replace the 2P-10B handswitch, the "B" RHR Pump control switch.
This handswitch has a history of not operating smoothly, and this was addressed in the past through the use oflubricants. A change in maintenance philosophy prompted the replacement of this component.
Completion Timine: This should be completed prior to the Unit 2 core loading.
Criteria to Closcout This Item:
- 1. Completion of the work associated with the listed work order.
- 2. The Responsible Person has forwarded the followirg documentation to the Restart ;
Issues Coordinator: l l
e A copy of page 2 from the closed work order (the Duty Shift Supervisor's l
signature and date in the " Equipment Return to Service" section indicates that the associated equipment is operable).
- A summary of the significant items / issues identified during conduct of the work order and how they were resolved (can simply reference Condition Report numbers or other ' racking mechanisms) OR a statement that there were none identified (report using the NUTRK system - NUTRK U2R22 RESTART Action #66).
- 3. The Restart Issues Coordinator has verified that the:
- Restart issues File includes the documentation which the Responsible Person is required to forward to the Restart Issues Coordinator (see immediately above).
. Duty Shift Supervisor's signature and date is on the " Equipment Retum to Service" section on page 2 of the associated work order.
. Significant items / issues identified during conduct of the work order are being tracked in a tracking system which is being reviewed per Restart Commitment #20.
- 4. Completion of an independent verification. This will verify that:
- Problems identified or created by the activity are captured.
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- The scope of work performed reflects the wording of the Restart Commitment. If l not, document the rationale for the difference and identify the safety implications.
l . Documentation in the Restart File is adequate to support external verification l (NRC) activities.
- Appropriate training was completed.
l Status:
As of January 28,1997, the physical work is complete, and the work order is awaiting PMT.
The scheduled completion date is February 8,1997.
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f Point Beach Nuclear Plant Unit 2 Restart Commitment l Summary (February 5,1997)
! Commitment ID#: 67
! Commitment
Description:
The work and testing associated with these work orders will be completed prior to the associated component / system being declared operable: Work Orders 9611198 and 9611199 - repair the body-to-bonnet boric acid leak on CV-307 B (lowside tap for "B" RCP #1 seal d/p) and CV-308B (lap seal d/p for "B" RCP).
This is a housekeeping issue, not an operability issue. Resolution will bring this into compliance with Maintenance Department housekeeping standards.
Completion Timing: This should be completed prior to Unit 2 leaving cold shutdown.
Criteria to Closcout This Item:
- 1. Completion of the work associated with the listed work orders.
- 2. The Responsible Person has forwarded the following documentation to the Restart issues Coordinator:
. A copy of page 2 from the closed work orders (the Duty Shift Supervisor's signature and date in the " Equipment Return to Service" section indicates that the associated equipment is operable).
- A summary of the significant items / issues identified during conduct of the work order and how they were resolved (can simply reference Condition Report numbers or other tracking mechanisms) OR a statement that there were none identified (report using the NUTRK system - NUTRK U2R22 RESTART Action #67).
- 3. The Restart issues Coordinator has verified that the:
- Restart Issues File includes the documentation which the Responsible Person is required to forward to the Restart Issues Coordinator (see immediately above).
- Duty Shift Supervisor's signature and date is on the " Equipment Return to Service" section on page 2 of the associated work orders.
. Significant items / issues identified during conduct of the work orders are being tracked in a tracking system which is being reviewed per Restart Commitment #20.
- 4. Completion of an independent verification. This will verify that:
- Problems identified or created by the activity are captured.
135
e The scope of work performed reflects the wording of the Restart Commitment. If not, document the rationale for the difference and identify the safety implications.
- Documentation in the Restart File is adequate to support external verification (NRC) activities.
. Appropriate training was completed.
Statun l
As of January 28,1997, the physical work is complete, and the work order is awaiting i PMT. ;
l The scheduled completion date is February 8,1997. I I
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Point Beach Nuclear Plant Unit 2 Restart Commitment Summary (February 5,1997)
Commitment ID#: 68 Commitment
Description:
Repair valve AR-3511 per Work Order 9513340. The Unit 2 priming air ejector is blank flanged due to air in-leakage through the condenser air removal isolation valve, AR-3511. This resolves a workaround issue.
Completion Timine: This should be completed prior to Unit 2 leaving cold shutdown.
Criteria to Closeout This Item:
- 1. Completion of the work associated with the listed work order.
- 2. The Responsible Person has forwarded the following documentation to the Restart Issues Coordinator:
. A copy of page 2 from the closed work order (the Duty Shift Supervisor's signature and date in the " Equipment Return to Service" section indicates that the associated equipment is operable).
. A summary of the significant items / issues identified during conduct of the work order and how they were resolved (can simply reference Condition Report numbers or other tracking mechanisms) OR a statement that there were none identified (report using the NUTRK system - NUTRK U2R22 RESTART Action #68).
- 3. The Restart Issues Coordinator has verified that the:
. Restart Issues File includes the documentation which the Responsible Person is required to forward to the Restart issues Coordinator (see immediately above). l
. Duty Shift Supervisor's signature and date is on the " Equipment Return to Service" section on page 2 of the associated work order.
- Significant items / issues identified during conduct of the work order are being tracked in a tracking system which is being reviewed per Restart Commitment #20.
- 4. Completion of an independent verification. This will verify that:
. Problems identified or created by the activity are captured.
. The scope of work performed reflects the wording of the Restart Commitment. If not, document the rationale for the difference and identify the safety implications.
. Documentation in the Restart File is adequate to support external verification (NRC) activities.
. Appropriate training was completed.
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As of January 28,1997, the physical work associated with this work order is complete, and it is awaiting PMT.
The scheduled completion date is February 20,1997.
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Point Beach Nuclear Plant Unit 2 Restart Commitment Summary (February 5,1997)
Commitment ID#: 69 Commit.nent
Description:
Repair the drain valve for the heating steam moisture separator per Work Order 9613451.
The Unit 2 heating steam moisture separator level has been difficult to maintain during normal operations. Frequent Main Control Board alarms have been received due to low level, countering the station's attempt to maintain a black board policy. This will be tested following Unit 2 startup.
Completion Timine: This should be completed prior to Unit 2 leaving cold shutdown.
Crikria to Closcout This Item;
- 1. Completion of the work associated with the listed work order.
- 2. The Responsible Person has forwarded the following documentation to the Restart Issues Coordinator:
1
- A copy of page 2 from the closed work order (the Duty Shift Supervisor's signature and date in the " Equipment Return to Service" section indicates that the associated equipment is operable).
- A summary of the significant items / issues identified during conduct of the work order and how they were resolved (can simply reference Condition Report numbers or other tracking mechanisms) OR a statement that there were none identified (report using the NUTRK system - NUTRK U2R22 RESTART Action #69).
- 3. The Restart Issues Coordinator has verified that the:
- Restart issues File includes the documentation which the Responsible Person is required to forward to the Restart Issues Coordinator (see immediately above).
- Duty Shift Supervisor's signature and date is on the " Equipment Return to Senice" section on page 2 of the associated work order. !
. Significant items / issues identified during conduct of the work order are being tracked in a tracking system which is being reviewed per Restart Commitment #20.
l 4. Completion of an independent verification. This will verify that:
- Problems identified or created by the activity are captured.
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. The scope of work performed reflects the wording of the Restart Commitment. If l not, document the rationale for the difference and identify the safety implications.
l . Documentation in the Restart File is adequate to support extemal verification (NRC) activities.
- Appropriate training was completed. l Status:
l As of January 28,1997, the physical work. associated with this work order is scheduled to start on February 11 and complete February 12.
The scheduled completion date is February 15,1997.
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Point Beach Nuclear Plant Unit 2 Restart Commitment Summary (February 5,1997)
Commitment ID#: 70 -
Commitment
Description:
Install a new level control system for the brine tank (T-118) per Modification 92-008*Q.
The tank overflows because the installed automatic level control system is not effective, and there is no high-high level alarm for the tank. This has been a recurring human performance issue exasperated by design. This modification will minimize the human performance challenges.
Completion Timine: This should be in an accepted status prior to the Unit 2 approach to criticality.
Criteria to Closcout This Item:
- 1. The modification is in an accepted status.
- 2. The Responsible Person has forwarded the following documentation to the Restart Issues Coordinator:
. A copy ' f the Installation Work Package page which shows the Duty Shift Supen ,or's acceptance of the modification.
- A sum nary of the significant items / issues identified during conduct of the modification and how they were resolved (can simply reference Condition Report numbers or other tracking mechanisms) QR a statement that there were none identified (report using the NUTRK system - NUTRK U2R22 RESTART Action
- 70).
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- 3. The Restart Issues Coordinator has verified that the: !
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. Restart Issues File includes the documentation which the Responsible Person is j required to forward to the Restart issues Coordinator (see immediately above).
+ Duty Shift Supervisor's signature and date is on the copy of the Installation Work Package page.
- Significant items / issues identified during conduct of the modification are being tracked in a tracking system which is being reviewed per Restart Commitment #20.
- 4. Completion of an independent verification. This will verify that:
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- Problems identified or created by the activity are captured. l l
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l . The safety evaluation reflects the scope of work completed.
. The scope of work performed reflects the wording of the Restart Commitment. If not, document the rationale for the difference and identify the safety implications.
. Documentation in the Restart File is adequate to support external verification (NRC) activities.
. Appropriate training was completed.
. Procedure updates identified in the modification package were completed.
Status:
As of February 5,1997, the modification is partially complete. The high-high level switch has been installed and tested satisfactorily. Ilowever, attempts to repair the normal level control system were unsuccesful, and Engineering Change Request 97-008 has been initiated to modify the brine tank standpipe to improve level equilization between the standpipe and the bulk of the tank.
Preparation of the work plan, safety evaluation, and other documents is in progress. The standpipe modification is scheduled for February 5,1997.
The scheduled completion (acceptance) date is February 17,1997.
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Point Beach Nuclear Plant Unit 2 Restart Commitment 1 Summary (February 5,1997) !
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{ Commitment ID#: 71 l
, Commitment Descrintion: Repair MS-249, the Unit 2 steam line sample valve, per l Work Order 9603128.
1 This valve had a packing leak, which required steam header sampling to be shifted to the j B steam header. This repair will restore the ability to sample normally and resolves a '
workaround issue. ,
l Completion Timine: This should be completed prior to Unit 2 leaving cold shutdown. I Criteria to Closcout This Item:
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- 1. Completion of the work associated with the listed work order. )
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- 2. The Responsible Person has forwarded the following documentatien to the Restart Issues Coordinator: l
. A copy of page 2 from the closed work order (the Duty Shift Supervisor's signature and date in the " Equipment Return to Service" section indicates that the associated equipment is operable).
. A summary of the significant items / issues identified during conduct of the work order and how they were resolved (can simply reference Condition Report numbers or other tracking mechanisms) OR a statement that there were none identified (report using the NUTIUC system - NUTRK U2R22 RESTART Action #71).
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- 3. The Restart Issues Coordinator has verified that the:
. Restart Issues File includes the documentation which the Responsible Person is required to forward to the Restart Issues Coordinator (see immediately above).
. Duty Shift Supervisor's signature and date is on the " Equipment Return to Service" section on page 2 of the associated work order.
. Significant items / issues ideatified during conduct of the work order are being tracked in a tracking system which is being reviewed per Restart Commitment #20.
- 4. Completion of an independent verification. This will verify that:
. Problems identified or created by the activity are captured.
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. The scope of work performed reflects the wording of the Restart Commitment. If not, document the rationale for the difference and identify the safety implications.
. Documentation in the Restart File is adequate to support external verification (NRC) activities.
. Appropriate training was completed.
Status:
As of January 28,1997, the physical work is complete, and the work order is awaiting PMT.
The scheduled completion date is February 20,1997.
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Point Beach Nuclear Plant Unit 2 Restart Commitment Summary (February 5,1997)
Commitment ID#: 72 Commitment
Description:
Repair alarm switch 2LS-2511 per Work Order 9605711.
The Unit 2 D MSR level was being maintained low in ti. band due 'o level oscillations and a steam leak from the alarm switch.
Completion Timine: This should be completed prior to Unit 2 leaving cold shutdown.
Criteria to Closcout This Item:
- 1. Completion of the work associated with the listed work order.
- 2. The Responsible Person has forwarded the following documentation to the Restart Issues Coordinator:
. A copy of page 2 from the closed work order (the Duty Shift Supervisor's signature and date in the " Equipment Return to Service" section indicates that the associated equipment is operable).
. A summary of the significant items / issues identified during conduct of the work order and how they were resolved (can simply reference Condition Report numbers or other tracking mechanisms) DJ1 a statement that there were none identified (report using the NUTRK system - NUTRK U2R22 RESTART Action #72).
- 3. The Restart Issues Coordinator has verified that the:
. Restart Issues File includes the documentation which the Responsible Person is required to forward to the Restart Issues Coordinator (see immediately above). )
. Duty Shift Supervisor's signature and date is on the " Equipment Return to Service" section on page 2 of the associated work order.
. Significant items / issues identified during conduct of the work order are being tracked in a tracking system which is being reviewed per Restart Commitment #20.
- 4. Completion of an independent verification. This will verify that:
. Problems identified or created by the activity are captured.
. The scope of work performed reflects the wording of the Restart Commitment. If not, document the rationale for the difference and identify the safety implications.
. Documentation in the Restart File is adequate to support external verification (NRC) activities.
. Appropriate training was completed.
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1 Status:
As of January 28,1997, the physical work is complete, and the work order is awaiting P M T.
The scheduled completion date is February 20,1997, t
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Point Beach Nuclear Plant Unit 2 Restart Commitment Summary (February 5,1997)
Commitment ID#: 73 Cummitment Descriptian: Repair 2P116, the Unit 2 Boric Acid Recirculation Pump, per Work Order 9603130.
There have been recurrent, significant seal leaks due to the pump's design and application. This work order replaces the current pump with a seal-less pump.
Completion Timing: This should be completed prior to Unit 2 leaving cold shutdown.
Criteria to Closcout This Item:
- 1. Completion of the work associated with the listed war der.
- 2. The Responsible Person has forwarded the following documentation to the Restart Issues Coordinator:
. A copy of page 2 from the closed work order (the Duty Shift Supervisor's signature and date in the " Equipment Retum to Service" section indicates that the associated equipment is operable).
- A summary of the significant items / issues identified during conduct of the work order and how they were resolved (can simply reference Condition Report numbers I or other tracking mechanisms) QR a statement that there were none identified (report using the NUTRK system - NUTRK U2R22 RESTART Action #73).
- 3. The Restart Issues Coordinator has verified that the:
. Restart Issues File includes the documentation which the Responsible Person is required to forward to the Restart Issues Coordinator (see immediately above).
. Duty Shift Supervisor's signature and date is on the " Equipment Return to Service" section on page 2 of the associated work order.
. Significant items / issues identified during conduct of the work order are being ,
tracked in a tracking system which is being reviewed per Restart Commitment #20. '
- 4. Completion of an independent verification. This will verify that:
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- Problems identified or created by the activity are captured.
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- The scope of work performed reflects the wording of the Restart Commitment. If not, document the rationale for the difference and identify the safety implications.
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i e Documentation in the Restart File is adequate to support external verification (NRC) activities.
l e Appropriate training was completed.
1 Status:
As of January 28,1997, the physical work associated with this work order is on parts I hold Oia. p.o ts are on site, but are awaiting seismic determination).
1 The scheduled completion date is February 20,1997.
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Point Beach Nuclear Plant Unit 2 Restart Commitment l
Summary (February 5,1997) l Commitment ID#: 74 Commitment
Description:
Each operating crew will receive simulator training to gain proficiency in casualty response, the expected response of the newly installed steam generators and reactor core, and placing the turbine on-line.
This simulator training will consist of:
- Bringing the turbine on-line (from the POAH to about 15% power).
. Reviewing the differences in steam generator response between Units 1 and 2.
. Conducting normal trips and identifying the differences in response between Units 1 and 2.
. Addressing instrument failure response differences between Units 1 and 2.
. Conducting casualty response dynamic scenarios in the training mode.
Completion Timingt This will be completed prior to the Unit 2 approach to criticality.
Criteria to Closcout This Item:
- 1. Completion of the training defined in the " Commitment Description" section.
- 2. The Responsible Person has forwarded the following documentation to the Restart Issues Coordinator:
. A summary / document describing what was covered in the simulator training (report using the NUTRK system - NUTRK U2R22 RESTART Action # 74).
. Copies of the attendance sheets for the simulator training.
. Significant items / issues identified during conduct of this task and how they were resolved (can simply reference Condition Report numbers or other tracking mechanisms) OR a statement that there were none identified (report using the NUTRK system - NUTRK U2R22 RESTART Action #74).
- 3. The Restart Issues Coordinator has verified that the:
- Restart Issues File includes the documents which the Responsible Person is required to forward to the Restart Issues Coordinator (see immediately above).
- Significant items / issues identified during conduct of the review are being tracked in a tracking system which is being reviewed per Restart Commitmew. #20.
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- 4. Completion of an ir. dependent verification.
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The crew training commenced on January 13,1997 as part of LOR training cycle 97-1.
! The operating crews will be trained during their normal requalification weeks, unless it l appears that they will not receive the training before the approach to criticality. In that case,just-in-time training will be conducted.
l Additionti y the crews designated to conduct the startup will be provided with startup training by ? 4:oruary 17,1997.
The scheda!ed completion date is February 20,1997.
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Point Beach Nuclear Plant Unit 2 Restart Commitment Summary (February 5,1997)
Commitment ID#: 75 Gunmitment
Description:
Revise the initial and requalification operator training plans to inciude a review of the administrative procedures identified as significant to daily operation of the plant during each two year operations training plan.
This commitment is also Enforcement Conference Commitment Item # 20.
Completion Timine This should be completed prior to the Unit 2 approach to criticality.
Criteria to Closeout This Item: ,
- 1. Completion of the task defined in the " Commitment Description" section.
- 2. The Responsible Person has forwarded the following to the Enforcement Conference Commitments Coordinator:
. A copy of the initial and requalification operator training plans which includes a review of the administrative procedures identified as significant to daily operation of the plant during each two year operations training plan.
. When the actions described in the " Commitments Description" section were completed (report using the NUTRK system).
. Significant items / issues identified during conduct of this task and how they were resolved (can simply reference Condition Report numbers or other tracking mechanisms) OR a statement that there were none identified (report using the NUTRK system).
- 3. The Restart Issues Coordinator or the Enforcement Conference Commitments Coordinator have verified that the:
. Restart Issues File includes the documents which the Responsible Person is required to forward to the Enforcement Conference Commitments Coordinator (see immediately above). 1
. Significant items / issues identified during conduct of the review are being tracked in a tracking system which is being reviewed per Restart Commitment #20.
- 4. Completion of an independent verification.
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Status:
Verified closed by the Enforcement Conference Commitments Coordinator.
l l The associated documentation was provided to the NRC in the January 24,1997 weekly l management meeting.
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i Point Beach Nuclear Plant Unit 2 Restart Commitment Summary (February 5,1997) l Commitment ID#: 76 l Commitment
Description:
Conduct roundtable discussions with all MSS \SS\DTA l personnel regarding conservative decisionmaking Technical Specification interpretations, and lessons learned from recent regulatory communications and perspectives. Review outlier Technical Specification interpretations for interim applications.
Completion Timine: This should be completed prior to the Unit 2 fuel loading.
Criteria to Closcout This item:
- 1. Completion of the roundtable discussions dermed in the " Commitment Description" section.
- 2. The Responsible Person has forwarded the following documentation to the Restart Issues Coordinator:
- A summary / document describing what was covered in the roundtable discussions (report using the NUTRK system - NUTRK U21'22 RESTART Action # 76).
. Copies of the attendance sheets for the roundtable discussions.
. Significant items / issues identified during conduct of this iasx and how they were resolved (can simply reference Condition Report numbers or other tracking ]
mechanisms) DR a statement that there were none identified (report using the )
NUTRK system - NUTRK U2R22 RESTART Action # 76). l
- 3. The R.estart issues Coordinator has verified that the:
- Restart Issues File includes the documents which the Responsible Person is required to forward to the Restart Issues Coordinator (see immediately above).
- Significant items / issues identified during conduct of the review are being tracked in a tracking system which is being reviewed per Restart Commitment #20.
- 4. Completion of an independent verification.
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l Status:
As of February 5,1997, prepaiations are in progress. The first meeting is scheduled for February 6.
This is scheduled to be completed by February 14,1997.
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Point Beach Nuclear Plant Unit 2 Restart Commitment Summary (February 5,1997)
Commitment ID#: 77 Commitment
Description:
Complete the procedure changes and training associated with the new Technical Specification on ECCS regarding the new Containment Integrity Analysis.
This involves the implementation of Technical Specification Change Request 192.
l Completion Timine: This should be completed prior to Unit 2 leaving cold shutdown.
Criteria to Closcout This Item:
- 1. Completion of the procedure changes and training defined in the " Commitment <
Description" section.
- 2. The Responsible Person has forwarded the following documentation to the Restart Issues Coordinator:
- A copy of the revised procedures.
- A summary / document describing what was covered in the training (report using the NUTRK system - NUTRK U2R22 RESTART Action # 77). :
- Copies of the attendance sheets for the training.
- Significant items / issues identified during conduct of this task and how they were i resolved (can simply reference Condition Report numbers or other tracking i mechanisms) OR a statement that there were none identified (report using the NUTRK system - NUTRK U2R22 RESTART Action # 77).
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- 3. The Restart Issues Coordinator has verified that the:
. Restart Issues File includes the documents which the Responsible Person is required to forward to the Restart Issues Coordinator (see immediately above).
- Significant items / issues identified during conduct of the review are being tracked in a tracking system which is being reviewed per Restart Commitment #20.
- 4. Completion of an independent verification.
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[ Status: 4 l
j .As of February 5,1997, work is in progress.
The scheduled completion date is March 3,1997.
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Point Beach Nuclear Plant Unit 2 Restart Commitment Summary (February 5,1997)
Commitment ID#: 78 Commitment Descriptinm Communicate specific expectations regarding AFW and EDG status control to Operators.
For the AFW status control, when the P-29 TDAFP should be declared operable has caused confusion, since the ability to FULLY test it for flow is not available until afkr reactor criticality. That delay in achieving a full flow test has been a confusing point.
The Technical Specifications and procedures are adequate.
The EDG status control issue involves AFW pumps tripping on overcurrent when lightly loaded and in an overfrequency condition, causing a loss of the associated AFW pumps.
Completion Timine: This should be completed prior to Unit 2 leaving cold shutdown.
Criteria to Closeout This Ittuu ;
- 1. Completion of the communication of specific expectations defined in the
" Commitment Description" section.
- 2. The Responsible Person has forwarded the following documentation to the Restart Issues Coordinator:
. A summary / document describing what was covered in the communications (report using the NUTRK system - NUTRK U2R22 RESTART Action # 78).
. Significant items / issues identified during conduct of this task and how they were resolved (can simply reference Condition Report numbers or other tracking mechanisms) OR a statement that there were none identified (report using the NUTRK system - NUTRK U2R22 RESTART Action # 78).
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- 3. The Restart Issues Coordinator has:
e Verified that the Restart issues File includes the documents which the Responsible Person is required to forward to the Restart Issues Coordinator (see immediately above).
. Verified that the significant items / issues identified during conduct of the review are being tracked in a tracking system which is being reviewed per Restart Commitment #20.
- Determined that all Operators were informed of these expectations.
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- 4. Completion of an independent verification.
Status:
As of February 5,1997:
. The AFW status control expectations have been disseminated via E-Mail.
. it has been found that keeping the AFW pump flowrates less than 250 gpm will prevent the overcurrent condition. This will be disseminated to operators through classroom training (as part of the SOER 96-01 training), as an Operations Notebook entry to explain the controls, and the EOPs will be revised to reflect this.
The scheduled completion date is February 28,1997.
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Point Beach Nuclear Plant Unit 2 Restart Commitment Summary (February 5,1997) ,
Commitment ID#: 79 Commitment
Description:
Restore a proceduralized capability to operate the
, Containment Spray Pumps in the recirculation mode of the ECCS. This will be included l procedurally in the EOP package.
l Completion Timine: This should be completed prior to Unit 2 leaving cold shutdown.
l r Criteria to C!oscout This Ittnu l
- 1. Completion of the task defined in the "Com.mitment Description" section.
- 2. The Responsible Person has forwarded the following documentation to the Restart Issues Coordinator:
- A summary addressing when the actions described in the " Commitments Description" section were completed and what specifically was done to accomplish the task (report using the NUTRK system - NUTRK U2R22 RESTART Action #
79). !
- Documents initiated or changed as a result of this task. The identification number for each of these must be included in this summary, and a copy sent to the Restart l Issues Coordinator for inclusion in the Restart issues File. l
- Significant items / issues identified during conduct of this task and how they were resolved (can simply reference Condition Report numbers or other tracking mechanisms) 2 a statement that there were none identified (report using the NUTRK system - NUTRK U2R22 RESTART Action # 79).
- 3. The Restart Issues Coordinator has verified that the:
- Restart issues File includes the documents which the Responsible Person is required to forward to the Restart issues Coordinator (see immediately above).
- Significant items / issues identified during conduct of the review are being tracked in a tracking system which is being reviewed per Restart Commitment #20.
l 4. Completion of an independent verification.
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Status:
l As of February 5,1997, Calculation #96-0270 has been completed which addresses the purnp NPSH and runout issues. The following actions are planned:
l e The calculation was done for Unit 1. It needs to be made applicable to Unit 2. I e The calculation predicts high RHR pump flowrates. An RilR high flow test will be conducted on February 6 to determine the rnaximum flowrate available. A 1 manufacturer representative will be present during conduct of the test. )
e Procedure CSPZ.1 is being drafted to address the changes. )
1 This will apply to the use of Containment Spray Pumps during elevated Contamment I I
pressures.
i This is scheduled to be completed by February 21,1997.
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Point Beach Nuclear Plant Unit 2 Restart Commitment
, Summary (February 5,1997) l l
Commitment ID#: 80 Commitment Desc iption: Obtain amendments requested by Change Requests 188 and 189 related to Steam Generator replacement; 192 related to Service Water operability; and 194 related to Low Temperature Overpressurization limits. This will include !
resolution ofissues related to Control Room and offsite dose evaluations for the analyzed j events.
l Completion Timine: This should be completed prior to Unit 2 leaving cold shutdown.
Criteria to Closcout This Item:
- 1. Completion of the task defined in the " Commitment Description" section.
- 2. The Responsible Person has fonvarded the following documentation to the Restart issues Coordinator:
. When the actions described in the " Commitments Description" section were completed (report using the NUTRK system - NUTRK U2R22 RESTART Action
- 80).
. A copy of the amendments.
. Significant items / issues identified during conduct of this task and how they were resolved (can simply reference Condition Report numbers or other tracking mechanisms) OR a statement that there were none identified (report using the NUTRK system - NUTRK U2R22 RESTART Action # 80).
- 3. The Restart issues Coordinator has verified that the:
- Restart Issues File includes the documents which the Responsible Person is required to forward to the Restart issues Coordinator (see immediately above).
. Significant items / issues identified during conduct of the review are being tracked in a tracking system which is being reviewed per Restart Commitment #20.
- 4. Completion of an independent verification.
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l l S.latun l As of February 5,1997:
. The supplement to Change Request 194 was sent to the NRC on January 27,1997, which involved an updated Reg. Guide 1.99 calculation.
- The environmental assessment for an N514 code case exemption related to Change Request 194 was noticed by the NRC.
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- LOCA dose calculations are being performed to support Technical Specification Change Requests 188,189, and 192 to be provided to the NRC by late-January 1997.
- A team has been formed to address control room ventilation dose concerns with the Operators.
This is scheduled to be completed by February 24,1997.
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Point Beach Nuclear Plant Unit 2 Restart Commitment Summary (February 5,1997)
Commitment ID#: 81 i
Commitment
Description:
Submit the following requests for license amendments resulting from the review of existing Technical Specification interpretations:
l . Revise the maximum acceptable power level when crossover steam dumps are inoperable (TS 15.3.4.E).
- Revise requirements for offsite power lines availability to address adequacy (TS 15.3.7.A. l .a).
- Remoie allowances in TS 15.3.1.A.l.a for single reactor coolant pump operation.
- Appropriately modify the minimum required boron concentration in the Refueling Water Storage Tanks.
Cmnpletion Timine: This should be completed prior to the Unit 2 approach to criticality.
Criteria to Closeout This Item:
- 1. Completion of the task defined in the " Commitment Description" section.
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- 2. The Responsible Person has forwarded to the Restart Issues Coordinator a copy of the l requests for th:: license amendments. i i
- 3. The Restart Issues Coordinator has verified that the:
- Restart issues File includes the documents which the Responsible Person is required to forward to the Restart Issues Coordinator (see immediately above).
. Significant items / issues identified during conduct of the review are being tracked in a tracking system which is being reviewed per Restart Commitment #20.
- 4. Completion of an independent verification.
Status:
l As of February 5,1997, work is in progress:
l l . The crossover steam dumps have been assigned and will be Technical Specification l Change Request 196. This was approved on February 4 by staff. Awaiting offsite committee review.
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e Single RCP operation and offsite power is being drafted.
. The RWST boron concentration issue has been submitted to the NRC.
This is scheduled to be completed by February 24,1997.
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e c POINT BEACH UNIT 2 RESTART COMMITMENT :
INDEPENDENT REVIEW RESULTS
- Commitment ID Number 65 Commitment Description 1
The work and testing associated with this work order will be completed prior to the associated 1
component / system being declared operable: Work Order 9606626 - reinstall switches on the Unit 2 Containment hatch third door to allow monitoring of door status.
There have been recurring human performance errors associated with this door, as people would block it open during refueling operations to transfer equipment. To ensure the operability of this door, switches are being installed to allow remote monitoring ofits status.
Reviewer Review Methodology Reviewed completed Work Order (WO) 9606626, and discussed with responsible person.
Walked down completed installation.
Verified no Condition Reports (CRs) generated in performance of WO 9606626.
Review Results WO completed, based on review of documentation, responsible person input, and field walkdowns.
No CRs generated as a result of doing this work.
One clarification is that the Restart Commitment describes the rationale for installing the magnetic )
switches on the Containment hatch third door. This modification was done previously and is not part of WO 9606626. WO 9606626 only removed / reinstalled the switches and adjoining cable / conduit i inside the equipment hatch (26' elevation) to allow for equipment hatch removal for the steam I generator replacement.
All work reviewed for this Restart Commitment is adequate.
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- t POINT BEACH UNIT 2 RESTART COMMITMENT i INDEPENDENT REVIEW RESULTS Commitment ID Number 65
, Recommendations t l Clarify Commitment Description for WO 9606626 for removal / reinstallation of magnetic switches only. For background for why switches were installed, should clarify that this modification was done
, previously.
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, Based on this independent review, there are no items involved with Restart Commitment #65 which would impede Unit 2 startup.
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Page 2 of 2
. 6s ORIfeINAL **uc*o**** PBNP ********** WO No: 9606626001 WO Priority: M
- UNIT 0
- MWO
- UNIT 0 * ;
Resp Grcup: IC ********** STEP DETAIL ********** Step Print: 09/24/96 Eq u i p ment : D00R-235 System: SEC HP Zone: i iipment Name: DOOR Physical Location: 26/U2F/U2C AIR LOCK THIRD DOOR Sequence No: Oi Need Date Short Desc: DISCONNECT MAG SW/ REMOVE CONDUIT Sched Start Date:
=============================================================================== ,
PLAblNED : WORK PROCEDURES:
l Crew: I '
1 Shift: 2 Class: 330
_=====================:========================================================= _
Work Plan
Description:
! SEE ATTACHED WORK PLAN t l
===================================_=========__=====================
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============================================================================= 1 MTE: __________ __________ __________ QAR: __________ __________ __________
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ACTUAL USED: CREW: __ .T._____ __ __.. _ __ ______ ______ _ ______ __
J SHIFT: ___a_____ _________ _________ _________ __._______
l WORKER CLASS: _.3LQ____ _ ______ _______ _ __ ____ _________
NUMBEPs OF WORKERS: ___i - -________ _________ _________ _________
TOTAL HOURS: _1.________________________________.___._
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TTL EXPOSURE / STEP (MREM)- __.O________________________________-____.__
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PARTS USED LIST ATTACHED: Y/
WO TAGS REMOVED: Y/N/@ @ WORK COMPLETE DATE: 1.2./ G/St,c, EMPLOYEE NAME: _____7L________.___________.
EMPLOYEE NUMBER:!? Sta ksi.160
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- WORK COMPLETED
- Cause Failure Code: PM e aV, NRM / __ ____
- As Found-Out of Spec
- Y / N-/ @ Machine History Review Required: h. /N Failed Component . ,,d _ _
Corrective Action: RP/RE/___ ____ Downtime: ____ hrs LINE SUPERVISOR 'f_ l l $17 l $ l'a'- NAME: _____ [r M, ___ _____ DATE: N//8f/
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- EQUIPMCNT ETURN TO SE VI :
- 3rabitity Post Testing: ._______
l hb'UI.P. T AKEN 00. S - D ATE : __./_ /__ TIME: _ _ _ _ . _ RTN DAT WOLU.g
/ /__
_ TIME
! Operability Procs Performed ___._________ _______ ____ __._____ .___ .._____ _. _.
NON OPS SUPV: i ' ' l...' i_' _._______ DATE:
. NAME: ______ . ___.-
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A _ _.__ DATE: _j/M/fs DSS:
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POINT BEACH NUCLEAR PLANT UNIT 2 STARTUP COMMITMENT LIST February 6,1997 Status Update IDENTIFICATION AND RESOLUTION OF ISSUES PERTINENT TO REACTOR SAFETY The following actions will be taken prior to Unit 2 criticality, except as specifically noted. The scope of reviews will be examining the identified documents or items for accuracy and compliance with requirements. Should any reviews identify either generic issues or significant discrepancies which could negatively impact reactor safety, the scope of those reviews will be expanded. Where discrepancies are identified, appropriate corrective and preventive actions will be taken commensurate with their safety significance.
Commitment Description Status ID Number Complete a detailed Unit 2 Containment Materiel Condition Assessment, in progress. Scheduled I addressing housekeeping, system walkdowns, materiel condition, and completion date is Feb. 25, instrumentation. Extensive work inside Containment was conducted this outage 1997.
due to the Steam Generator replacement project.
Walkdown all accessible Unit 2 and common Maintenance Rule systems for In progress. Scheduled 2 adequate visual material condition. completion date is Feb. 25, 1997.
3 Walkdown all accessible Unit 2 and common systems for outstanding work order In progress.
tags.
Conduct as-built inspections of the electrical and 1&C components on the Unit 2 Work complete. In closcout 4 CVCS and CCW systems (Work Orders 9607322,9611140,9606548, and verification process.
9611139). ,
5 Complete Work Orders 9513222 through 9513225 to conduct inspections of Work complete. In closecut Appendix R alternate power transfer switches. verification process.
Complete Work Order 9604151 to perform foreign material exclusion inspections Work complete. In closcout 6 on the Unit 2 4160V safeguards bus 2A-06 and breakers. verification process.
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Complcte a review of Unit 2 administrative controls implementing or referencing Work in progress Scheduled 7 Technical Specifications to ensure Technical Specification requirements are completion date is Feb. 25, appropriately reflected in the administrative controls. 1997.
Review 20% of the Operations Technical Specification, Inservice Test, and In progress. Scheduled Operations Refueling Test related surveillance procedures, with concentration on completion date is Feb. 25, 8 those involving major equipment. Upgrade as necessary to include appropriate 1997. Conducting initial conditions, retum to service lineups, properly specified independent independent verification of verification, reviewing acceptance criteria, and Technical Specification work completed thus far.
implementation.
Review the In Service Testing (IST) acceptance criteria for the remaining IST Work and independent 9 pumps to ensure that the IST acceptance criteria meets the design basis / accident closecut verification analysis requirements. Make any changes necessary as a result of this review. completed.
Review the In Service Testing acceptance criteria for all IST valves to ensure that Work and independent 10 the IST acceptance criteria meets the design basis / accident analysis requirements. closeout verification Complete neccssary operability evaluations, revise procedures, and resolve Unit 2 completed.
equipment discrepancies.
Complete the following regarding installed instrumentation used in the IST Work and in'Jependent program: closecut verification completed.
. Identify the Unit 2 instaJed instruments used in the IST program.
I1 . Review the performance of the identified instmments over the last 3 years.
. Review the suitability of the instrumentation for use in the IST program.
- Review all IST pump hydraulic data over the past year for adverse trends.
As necessary, make changes as a result of these actions.
Review 20% of the surveillance procedures associated with safety significant non- Work in progress. Scheduled 12 pump and valve components (such as heat exchangers and fans) to ensure that the completion date is Feb.14, surveillance acceptance criteria satisfy the requirements of the plant design 1997.
basis / accident analysis. Make changes as necessary as a result of this review.
13 Review other operating procedures that contain maintenance activities and revise Work complete. In closecut as necessary to ensure PMT and QC are properly addressed by : hose procedures. verification process.
Review equipment return to service testing requirements prior to the following Preparations to perfomt the U2R22 mode change readiness reviews to ensure the required equipment is readiness reviews are in 14 ope-able prior to changing modes: core reload, leaving cold shutdown, and the progress. Will occur approach to criticality. approximately one week prior to each of the mode changes.
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Review 20% of the work orders performed since January 1,1995 on Unit 2 or In progress. Scheduled 15 common PSA safety significant systems (AFW, SW, EDG, I A,4.16 kv, gas completion date is Feb.10, turbine, and CCW) to verify adequate PMT was performed to ensure 1997.
system / component safety function.
Complete all Unit 2 Maintenance Rule related work order post-PMT reviews prior On-going reviews in progress.
16 to the approach to criticality. This will continue through the outage.
Review 50.59 screenings conducted in 1996. Upgrade those determined to require in progress. Scheduled 17 a 50.59 evaluation. completion date is Feb. 20, 1997.
Review outstanding JCOs. Perform operability determinations and 50.59 In progress. Scheduled 18 evaluations needed to address the issues. completion date is Feb. 21, 1997.
Conduct a review of 50.59 evaluations from this outage. Ensure all conditions of Initial review completed. On-19 the evaluations have been completed. going reviews in progress.
Tracking associated conditions through the outage.
Review items from existing open item lists (e.g., NUTRK) to identify potentially in progress. Restart related 20 degraded equipment. CRs (generated by this review ;
and emergent) will be tracked ;
here.
21 Review open items from the Design Basis Document development program. Work complete. In closcout verification process.
All open operability evaluations fbr Unit 2 and common equipment will be in progress. Restart issues !
22 reviewed for acceptable closure of the degraded equipment issue. Disposition will be identified by Feb. 7, outstanding issues in accordance with 10CFR50.59 and Generic Letter 91-18. 1997 and resolved prior to the associated outage milestones.
Review 20% of the Condition Reports closed since January 1,1995 which are in progress. Scheduled 23 associated with PSA safety significant systems for degraded equipment operability completion date is Feb.7, issues to ensure that we have adequately identitied and dispositioned operabilitv 1997.
issues.
Complete an additional Outage Safety Review for the startup phase of the outage. In progress. Scheduled 24 completion date is Feb.10.
1997.
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Conduct an integrated review of all outage licensing commitments (50.59's, In progress. Scheduled 25 enforcement conference items, Technical Specification Change Requests, and completion date is February Reload Safety Analysis). Ensure all requirements are met. 28,1997.
26 Revise ORT-3 and DCS 3.1.11 to ensure Technical Specification 15.4.6.A.2 Work complete. In closecut testing includes dynamic loading of the EDG with sequenced loads. verification process.
Test all EDGs in accordance with revised ORT-3 and DCS-3.1.11. Return the ORT-3 is scheduled to be 27 electrical systems to normal alignment prior to leaving cold shutdown. performed the week of Feb. 3, 1997.
Resolve the containment penetration commitments, including: In progress. Scheduled 28 completion date is Feb. 21,
. CP-32 (Containment penetration for Auxiliary Charging line). 1997.
. Penetration thermal reliefissue.
Complete a 50.59 evaluation for the existing CCW supply to the RCP seals as a In progress. Scheduled 29 safety function. completion date is Feb.10, 1997.
Update the diesel generator loading calculation N-91-016 to properly reflect the In progress. Scheduled 30 loading of the Containment Fan Coolers. completion date is Feb.15, 1997.
Evaluate the adequacy of coordination on the 120 VAC instrument bus system In progress. Scheduled 31 through a 50.59 or operability review. completion date is Feb.15, 1997.
Implement interim improvements for the Condition Reporting process, based on a in progress. Scheduled 32 review of assessments and identified recommendations for improving that process. completion date is Feb. 25, 1997.
Implement interim improvements for the 50.59 process to require that all In progress. Scheduled 33 screenings be either authored or reviewed by a member of the multi-disciplinary completion date is Feb.13, review team. 1997.
Upgrade Unit 2 operations checklists to include requirements for initials, time, and In progress. Scheduled 34 hte. During the review, verify that the checklists are technically correct. completion date is Feb.19, 1997.
35 Revise applicable IST program documents to prevent equipment from being Work complete. In closcout returned to service (declared operable) with vibrations in the alert range. verification process.
Revise NP 8.1.1, Work Order Processing, and NP 8.1.3, Post-Maintenance Testing Work complete. In closecut 36 to ensure post-maintenance testing , operability testing, and surveillance test verification process.
requirements are properly addressed.
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37 Include return to service testing in the plant schedule, both outage and nonoutage. -Work complete. In closcout verification process.
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COMPLETE PHYSICAL WORK WHICH SUPPORTS SAFE STARTUP AN_ D POWER OPERATIONS Modifications which Point Beach Nuclear Plant has identified as being significant to safety and scheduled for completion in U2R22 will be in an accepted status (i.e., the applicable physical work completed, post-maintenance testing completed satisfactorily, and the associated component / system being declared operable) prior to being required to be operable per Technical Specifications. These modifications are:
Commitment Description Status ID Number Modification 96-033 - replace control power transformers on Motor Control In progress. Scheduled 38 Centers 2B32 and 2B42. completion date is Feb.15, 1997.
Modification 90-048 - replace Boric Acid and Reactor Makeup Water In progress. Scheduled 39 totalizers, replace the CVCS control switch, replace flow indicators, and completion date is Feb. 7, refurbish flow controllers. This resolves an Operator workaround issue. 1997.
Modification 94-097 - remove six RCS loop drain valves. In progress. Scheduled 40 completion date is Feb. 28, 1997.
41 Modification 92-141 - relocate the RIIR flow cont-ol valve controllers on Work complete. In closcout 2CO3 for human factoring. verification process.
Modification 96-073 - seismically upgrade CCW, SI, RIIR, and RIIR/ letdown In progress. Scheduled 42 piping supports and remove an AFW snubber. completion date is Feb. 7, 1997.
Modification 94-066 - install a soft seat in containment isolation valve 2SI- Work complete. In closcout 43 834D, and add a relief valve and pressure regulator in the nitrogen supply line verification process.
to the SI accumulators. This resolves an Operator workaround issue.
Modification 96-065B - seismically upgrade the Refueling Water Storage In progress. Scheduled 44 Tank recirculation line. completion date is Feb. I1, 1997.
Modification 96-054 - install pressure gauges iri the service water return in progress. Scheduled 45 header from the Emergency Diesel Generator GOI and GO2 glycol coolers, completion date is Feb. 7.
and reset the throttle valves in that line. 1997.
Modification 96-022 - install a new 125 VDC feed to 480V safeguards bus Work complete. In closecut 46 2B03. verification process.
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47 Modification 94-055 - add seismic supports to the raceway between risers 56 Work complete. In closcout and 62 on C04 (Reactor and Primary Plant Control Board). verification process.
Modification 96-068B - eliminate containment heating steam and condensate in progress. Scheduled 48 return containment isolation valves. completion date is Feb.18, 1997.
Modification 96-053 - replace an elbow in the west service water header. Awaiting installation.
49 Scheduled completion date is Feb.13,1997.
50 Modification 95-070 - seismically upgrade the containment cooling fans and In progress.
filters.
51 Modification 96-026 - install, delete, and modify supports for feedwater, main Work complete. In closcout steam, and SI system piping for the 79-14 project. verification process.
52 Modification 96-058 - move Power Plant Computer System alarms to the Work complete. In closcout exterior of C-20 panels. verification process.
53 Modification 94-095 - replace 8 Main Steam Condenser steam dump valves Work complete. In closecut with improved design. verification process.
Modification 95-029 - replace Si accumulator level transmitters. In progress. Scheduled 54 completion date is Feb. 24 I997.
55 Modification 95-035 - modify Containment Spray additive tank controller Work complete. In closcout circuit. verification process.
Modification 96-063 - replace 345 KV breakers (3-4,4-5, and 142). Awaiting PMT (will not be 56 completed until Unit 2 is on-line).
Modification 96-069 - replace four breakers (l Y-06-01,1 Y-06-03, I Y-06-05, In progress. Scheduled 57 and 1 Y-06-11) associated with instrument bus 1 Y-06. completion date is Mar. 3, 1997.
58 Modification 95-058*O - repair Steam Generator intermediate leg supports. Work complete. In closecut This may be resolved through analysis. verification process.
Modification 96-070 - replace molded case circuit breakers associated with Work and PMT completed.
59 instrument buses 2Y-05 and 2Y-06. Scheduled completion date is Feb.8.1997.
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l The work and testing associated with these Work Orders will be completed prior to the associated component / system being declared operable.
l Emergent Work Orders associated with Maintenance Rule Risk Significant Systems which Point Beach Nuclear Plant defines as priority level I to 4 will be completed prior to Unit 2 criticality.
Commitment Description Status ID Number Work Orders 9601506,9602502,9603921,9611267,9611278, and 9611755 Work complete. In closcout 60 - replace proximity switches and targets with an improved design and verification process.
overhaul the Fuel Transfer Cart to enhance control system operation. This resolves an Operator workaround issue.
Work Orders 9613568 and 9613569 - provide bonnet pressure locking relief Awaiting PMT. Scheduled 61 for the SI-857A and SI-857B valves (interface valves between RilR and completion date is Feb.10, Iligh IIcad SI) on Unit 2. 1997.
Work Order 9611757 - correct the leakage which leads to boric acid buildup Awaiting PMT. Scheduled 62 in the cylinder blocks of"B" Charging Pump. completion date is Feb. 20, 1997.
Work Order 9603532 - repair the handswitch for 2P-2A, the "A" Charging Awaiting PMT. Scheduled 63 Pump. completion date is Feb. 20, 1997.
Work Orders 9611624 through 9611626 - replace existing pneumatic turbine Work is schedule . ~5e 64 generator circuitry time delay relays with plug-in, electronic time delay scheduled completion date is relays. Feb.24,1997.
65 Work Order 9606626 - reinstall switches on the Unit 2 Containment hatch Work complete. In closcout third door to allow monitoring of door status. verification process. !
Work Order 9611052 - replace the 2P-10B switch, the "B" RilR Pump Awaiting PMT. Scheduled 66 control switch. completion date is Feb. 8, 1997.
Work Orders Y611198 and 9611199 - repair the body-to-bonnet boric acid Awaiting PMT. Scheduled 67 leak on CV-307 B (lowside tap for "B" RCP #1 seal d/p) and CV-308B (lap completion date is Feb. 8, seal d/p for "B" RCP). 1997.
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r The following actions will be completed to correct Operator workarounds prior to Unit 2 criticality, except as spccifically noted:
Commitment Description Status ID Number i Repair valve AR-3511 per Work Order 9513340. The Unit 2 priming air Awaiting PMT. Scheduled 68 ejector is blank flanged due to air in-leakage through the condenser air completion date is Feb. 20, f removalisolation valve, AR-3511. 1997.
Repair the drain valve for the heating steam moisture separator per Work Scheduled to start on Feb. I 1, 69 Order 9613451. The Unit 2 heating steam moisture separator level has been 1997. Scheduled completion diflicult to maintain during normal operations, and frequent alarms were date is Feb. 15,1997.
received due to lo v level. This will be tested following Unit 2 startup.
Install a new level control system for the brine tank (T-118) per Modification In progress. Scheduled j 70 92-008*Q. The tank overflows because the installed automatic level control completion date is Feb.17, system is not efTective, and there is no high level alarm for the tank. 1997. ,
Repair MS-249, the Unit 2 steam line sample valve, per Work Order Awaiting PMT. Scheduled 71 9603128. The valve had a packing leak which required steam header completion date is Feb. 20, sampling to be shined to the B steam header. 1997. ;
Repair alarm switch 2LS-2511 per Work Order 9605711. The Unit 2 D MSR Awaiting PMT. Scheduled 72 level was being maintained low in the band due to level oscillations and a completio'n date is Feb. 20, !
steam leak from the alarm switch. 1997. !
Repair 2P116, the Unit 2 Boric Acid Recirculation Pump, per Work Order In progress. Scheduled 73 9603130. It has a significant seal leak. completion date is Feb. 20, 1997. i i
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PERSONNEL AND LICENSING READINESS The following actions will be completed prior to Unit 2 criticality:
i Commitment Description Status ID Number Each operating crew will receive simulator training to gain proficiency in In progress. Scheduled 74 casualty response, the expected response of the newly installed steam completion date is Feb. 20, generators and reactor core, and placing the turbine on-line. 1997.
Revise the initial and requalification operator training plans to include a Work complete. Conducting review of the administrative procedures identified as significant to daily independent closeout i operation of the plant during each two year operations training plan. verification (in addition to the :
75 verification already completed by the Enforcement Conference Commitments Coordinator). >
Conduct roundtable discussions with all MSS \SS\DTA personnel regarding In progress. Scheduled conservative decisionmaking, Technical Specification interpretations, and completion date is Feb.14, 76 lessons learned from recent regulatory communications and perspectives. 1997. t Review outlier Technical Specification interpretations for interim f ,
applications. ;
Complete the procedure changes and training associated with the new In progress. Scheduled 77 Technical Specification on ECCS regarding the new Containment Integrity completion date is March 3, Analysis. 1997.
Communicate specific expectations regarding AFW and EDG status control In progress. Scheduled 78 to Operators. completion date is Feb. 28, 1997. ;
Restore a proceduralized capability to operate the Containment Spray Pumps In progress. Scheduled 79 in the recirculation mode of the ECCS. completion date is Feb. 21, ,
1997. .
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Obtain amendments requested by Change Requests 188 and 189 related to In progress. SQeduled Steam Generator replacement; 192 related to Service Water operability; and completion date is Feb. 24, 80 194 related to Low Temperature Overpressurization limits. This will include 1997.
resolution ofissues related to Control Room and effsite dose evaluations for the analyzed events.
Submit the following requests for license amendments resulting from the In progress. Scheduled ,
review of existing Technical Specification interpretations: completion date is Feb. 24, 1997.
. Revise the maximum acceptable power level when crossover steam dumps are inoperable (TS 15.3.4.E).
1 . Revise requirements for ofTsite power lines availability to address adequacy (TS 15.3.7.A.I.a).
. Remove allowances in TS 15.3.1.A.I.a for single reactor coolant pump operation.
- Appropriately modify the minimum required boron concentration in the Refueling Water Storage Tanks.
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