ML030870670
| ML030870670 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 05/06/2002 |
| From: | Larson T, John Miller, Sokol K Nuclear Management Co |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| FOIA/PA-2003-0094, TCN-2002-0324 PBF-0026c | |
| Download: ML030870670 (15) | |
Text
Nuclear Power Business Unit TEMPORARY CHANGE REVIEW AND APPROVAL Notc" Refer to NP 1.2.3, Temporary Procedure Changes.for requirements. Page 1 of I - INITIATION Doc Number _*- /6/.,4 Current RevJ// Unitj Temp Chaplain. . y-Document Title 'j, ,E f ',,-"- /&--,/ ,',, , *, r. e,,/, ///.
"ill,/ &, ar' k 1-/i4--- .. . ",
Existing Effective Temporary Changes e/'7 ,
Brief Description ,c-/*.- / - _s .
(Identify specific changes on 1-rrm PBF-0026e Document Review and Approval Continuation, and include nZhthe package)
PBF-0026h and include with the change.
Other documents required to be effective concurrently with the temporary change: '% .,-*
Changes pre-screened according to NP 5.1.8? El NO WYES Provide documentation according to NP 5 19)
Screening completed according to NP 5.1.8? I*NA El YES (Attach copy)
Safety Evaluation Required? NO E YES (ifYes. aresion rmaybe processed or fnral rev*,*s andapprovals shall be obu*ned beforoimplmeneng)
Determine if the change constitutes a Change Of Intent to the procedure by evaluating the following questions.
(If any answers are YES, a revision may be processed or final reviews and approvals shall be obtained before implementing)
Will the proposed change: YES NO I. Require a change to, affect cr invalidate a requirement, commitment, evaluation or El description in the Current or ISFSI Licensing Basis (as defined in NP 5.1.8 and NP 5.1.7)7
- 2. Cause an increase in magnitude, significance or impact such that it should be processed as a revision?
- 3. Delete or modify a prerequisite, initial condition, precaution, limitation or other steps that could have safety significance or affect the procedure's margin of safety?
- 4. Delete QC hold points, Independent Verification or Concurrent Check steps without the related step(s) that require the performance also being deleted?
- 5. Change Tech Spec or other regulatory acceptance criteria other than for re-baselining [
purposes?
Group Supervisor (print/sign)--/p.tt 1 *. -ZI- I-Zg~I2 4 Date_____
(Cannot be the Initiator)
This change Senior Reactor Operator B(nninsign) does not adversely-i. affect Plant operating " conditions.
/'- / -Related procedures only) Date (Safety ____'_.,_-__
(Group Supervio)/sign) Date E Hold cchanie until procedure completend if approval still re ired wihin 14 days of initial approval)
Ap QRc/MSS Tindicates Review NOT appidivl not does7Required (AdrfNS anyfectPlant sessed, .. nly)
.QR speraetings/eoaditions.
Review RequI*S (afeyRelaed. Review Requiredtonly te)dtso penmnau~nmads -Ra ,
ProcedureThiq Owner (print/sign) pnleted and processeI " / Date Ch--nee and supponin2 iecoutre-Mints -corre*iliv com TV - FINAL REVIEW AND APPR VAL, completed witahin cha be nMust lngs approval) cT he Initiator, QR and AanVohan rrity callnb nr) eptendentofrd SIndicates 50.59/72-4S ipp'cbilhty assessed. any necessary scemefnmgs/cvaldtfions j~c-Aormed. dc"ie?-miatlon made as to whethef add~toaal MS etnAuthorityo (print/sign) (e--" ,_ *Approval - -0 a . i L Date sle'_Z V -REVISION INFORMATION FOR PERMANENT CHANGES F Post Typing Review (printisign) /Date l.-
Incorporated into Revision Number Effective Date
References:
NP 1.2.3 Rvsoi--U1U3O 6 Revision 13 011!6/02
Point Beach Nuclear Plant DOCUMENT REVIEW AND APPROVAL CONTINUATION
?a~e! of 3 Doc Number //4Revision Unit/
Title A7---sFtrLf,2 g! A/s~t A 67 Temporary Change Number A'P - 0 '2 Description of Chahges:
Step
- Change/Reason s-- $ri zXIAý~
,c<I*. , ~*,5*S~4,4~~ iW 27.,. ./ '*'*3. //!A ,/>-. * (
4/0 Other Comments
- Note: Recording of Step Numberts) is not required for multiple occurrences of identical information or when not beneficial to reviewers.
PBF-0026c
.NP
References:
NP 1.13. 1.2.3 Revision 6 04118/01
Point Beach Nuclear Plant TEMPORARY CHANGE AFFECTED MANUAL LOCATION Page0 _ of "
__________________________________ Revision Unit Procedure Number _ Revision/_ Unit Title C,,i , 7/, eEZ 7-' - a .i,. ,,v,/S,' *. A,,: Aer*..1 ,¢/56 Temporary Change Number .,Z?67. - 63,24" I - IMMEDIATELY AFTER INITIAL APPROVAL ON PBF-0026e (Non-Intent changes)
(after Final Approval if change of intent involved)
Date This procedure change has been processed as follows: (Manual/Location) Performed E] Copy included in work package for field implementation. (WO No. )
E] Copy filed in Control Room temp change binder (Operations only).
[] Original change package provided to 6, qz.-( to obtain Procedure Owner - -° ...
Review (e.g.. Owner review may be coordinated by In-Group OA 1, Procedure Writer. Procedure Supervisor. etc.).
El LI El El LI Performed By (print and sign) - /C . ec-,-, Date 5_- -c2..
II - PROCEDURE OWNER REVIEW ON PBF-0026e (may be performed by OA II, Procedure Writer, etc.)
Date This procedure change has been processed as follows: (Manual/Location) Performed El Copy sent to Document Control Distribution Lead for Master File.
(Not required for one-time use change)
E) Copy filed it Group satellite file. (Not required for one-time use changes.)
El Copy filed in Group one-time use file.
[] Original Temp Change provided to * . to obtain Final Approvals Z_..-
(e g. final approval may be coordinated by In-Group OA JL Procedure Writer. Procedure Supervisor. etc.)
Performed By (print and sign) *--, _t,.---- / .".'i,,(_. Date ,-- :,_-oZ..
PBF-0026h
Reference:
NP 12.3 Revision 5 06/13/01
Point Beach Nuclear Plant 10 CFR 50.59/72.48 PRE-SCREENING REVIEW Page ..f of__
Brief Activity Title or Temp Change to IT-10A
==
Description:==
This form is required to be completed and attached to the applicable activity change forms (i.e., PBF-0026a/c, etc.) to document use of Pre-screening Criterion 3 through 6 for 10 CFR 50.59 / 72 48 review of proposed changes (see NP 5.1.8, 10 CFR 50.59/72.48 Applicability, Screening and Evaluation (New Rule) Section 4.6 and Attachment A.)
Pre-screening Criterion 3 - Activity Covered by Existing 10 CFR 50.59 / 72A8 Screening or Evaluation Criterion 3 is Z Not Applicable to the proposed activity.
Identify the screening or evaluation number(s) (SE for old 50.59/72A8 rule evaluations, EVAL for new rule evaluations):
SCR / SE / EVAL #(s): SPEED # (NP 9.3.3, Rev. 3 or later ONLY):
If applicable, briefly summarize the parts of the proposed activity that are covered by Pre-screening Criterion 3.
Pre-screening Criterion 4 - Activity Covered by ExistingApproved and Valid Plant Procedure Criterion 4 is EQ Not Applicable to the proposed activity.
Identify the applicable plant procedure.
Procedure number, revision and title:
If applicable, briefly summarize the parts of the proposed activity that are covered by Pre-screening Criterion 4.
The temp change to IT-10 A was made so the test can be completed properly. Due to modifications to add backup nitrogen to the mini recirc valves, IT-10 was changed to include the newly added components. IT-IOA was not included in the list of procedures that needed to be updated as a result of this modification. This change has already been incorporated into IT-10 Rev 44 which was screened for nuclear safety and licensing implications. This change exactly matches what is in IT-10 for performing a shut test of.AF-133 and AF-153 Pre-screening Criterion 5 - NRC has Reviewed and Approved the Activity.
Criterion 5 is CK Not Applicable to the proposed activity.
Identify the NRC Safety Evaluation Report Number and/or Date.
NRC SER(s) # or Date(s):
If applicable, briefly summarize the parts of the proposed activity that are covered by Pre-screening Criterion 5.
Pre-screening Criterion 6 - Maintenance Activity (NOTE: Dry cask or ISFSI facility maintenance CANNOT use this criterion. A screening is required for dry cask or ISFSI facility maintenance.)
Criterion 6 is [D Not Applicable to the proposed activity.
If applicable, briefly summarize the parts-of the proposed activity that are covered by Pre-screening Criterion 6.
VERIFY THAT NONE OF THE FOLLOWING CHANGES ARE PRE-SCREENED TO CRITERION 6: Verified No changes to structure, system or component design, performance, acceptance criteria, types of materials, []
torque values outside of vendor recommended values, etc. (NOTE: Use Criterion 3 for SPEEDs.)
PBF-1515b Revision 1 04/03/02
Reference:
NP 5.1.8
Point Beach Nuclear Plant 10 CFR 50.59/72.48 PRE-SCREENING REVIEW P "f Page 2_of No temporary alterations to support maintenance or modification installation will be in place longer than 90 []
days. (If there is any doubt whether the temporary alteration will be removed in 90 days, perform a screening.)
No changes in acceptance criteria in technical specification surveillance or post-maintenance test procedures. []
10 CFR 50.59/72.48 PRE-SCREENING REVIEW CONCLUSION Preparer and Reviewer signatures below signify that the portions of the proposed activity as described above are within the scope of Prescreening Criteria 3, 4, 5, or 6 of NP 5.1.8.
EITHER preparer OR reviewer shall be 50.59/72.48 screening or evaluation qualified.
Performed By Ryan Rode /
- Date 05/04/2002 Name (Print) " ture Reviewed By / /*a" Seg>aZ-1r Date Name (Print) Signature PBF-1515b Revision 1 04/03/02
Reference:
NP 5.1.8
- *Point Beach Nuclear Plant PROCEDURE RECORD AND FIELD COPY TRACKING Record/Field Copy Identification Field Copy Number RED - Record Copy; BLACK - Field Copy Procedure Number 72T- IOA Unit I Revision Number /f(
Revision Date */u, /,,0ap, Procedure Title gfap6fep Procedure Revision Checked anjd Current; Vzo~ng,Checked for Teniporary ClhA~s:-'
By l.Y J 2 c0*j _________
Date s 4(d Record Copy Holder/Location Cc' / CQif(dI 3-FIELD COPY DISTRIBUTION Copy No. Holder/Location Issue Date Return Date 1 7ef4 (2-ad- A, 2
3 4
5 6
7 8
9 10 NOTE 1: ANY TEMPORARY CHANGES MADE TO THIS PROCEDURE SHALL BE MADE TO THE RECORD COPY AND ALL OTHER FIELD COPIES THAT HAVE BEEN ISSUED.
NOTE 2: RETURN ALL FIELD COPIES TO THE HOLDER OF THE RECORD COPY UPON PROCEDURE COMPLETION.
PBF-0026i
Reference:
NP 1.1.4 Revision 2 2/21101
r t
.. i IT 10A TEST OF ELECTRICALLY-DRIVEN AUXILIARY FEED PUMPS AND VALVES WITH FLOW TO UNIT 1 STEAM GENERATORS (QUARTERLY)
DOCUMENT TYPE: Technical CLASSIFICATION: Safety Related 11 REVISION:
EFFECTIVE DATE: July 5, 2001 REVIEWER: Qualified Reviewer APPROVAL AUTHORITY: Department Manager PROCEDURE OWNER (title): Group Head OWNER GROUP: Operations Verified Current Copy:
Signature Date Time List pages used for Partial Performance Controlling Work Document Numbers
POINT BEACH NUCLEAR PLANT IT 10A SAFETY RELATED INSERVICE TESTS Revision 11 July 5, 2001 TEST OF ELECTRICALLY-DRIVEN AUXILIARY FEED PUMPS AND VALVES WITH FLOW TO UNIT 1 STEAM GENERATORS (QUARTERLY)
INITIALS 4.0 INITIAL CONDITIONS 4.1 This test is being done to satisfy:
X" The normally scheduled callup. Task sheet No. 977 **-'.3 NOTE: If this test is being performed to satisfy PMT or off-normal frequency requirements, Shift Management may N/A those portions of the procedure that are NOT applicable for the performance of the PMT. The use of N/A is NOT acceptable for Initial Conditions, Precautions and Limitations, or procedure steps that pertain to the equipment requiring PMT, nor is it acceptable for restoration of equipment/components unless the component has been declared inoperable.
NOTE: If this test is being performed to satisfy pump PMT requirements any vibration levels above 0.325 ips measured at any ASME Section XI Code required location shall be evaluated by engineering prior to declaring the pump operable.
___ Post maintenance operability test Equipment ID WO No(s).
Task Sheet No.(s)
Special test - no numbers. Explain:
4.2 Auxiliary feed system lined up for critical operation per CL 13E Part 2, Auxiliary Feedwater Valve Lineup Motor-Driven..
4.3 Standby emergency power shall be available to the 4160 V safeguards buses 1A05, 1A06, 2A05, 2A06, or the component(s) to be tested is/are in the same train that is out of service.
4.4 Chemistry notified about auxiliary feed injection.
4.5 Reactor power reduced a minimum of 2% OR to a power level directed by DSS. (Mark step NIA if in CTS: Hot or Cold Shutdown {ITS: Modes 3,4, I 5, 6, & defueled})
4.6 Permission to Perform Test The conditions required by this test are consistent with required plant conditions, including equipment operability. Permission is granted to perform this test.
DSS N b101 TIME_____ DATE_614~/pi Page 5 of 53 CONTINUOUS USE
POINT BEACH NUCLEAR PLANT IT 10A SAFETY RELATED INSEERVICE TESTS Revision 11 July 5, 2001 TEST OF ELECTRICALLY-DRIVEN AUXILIARY FEED PUMPS AND VALVES WITH FLOW TO UNIT 1 STEAM GENERATORS (QUARTERLY)
INITIALS NOTE: Attachment L shall be used to document performance of multiple step performance and to record data. A separate copy of Attachment L shall be prepared for each step series requiring multiple performance and all copies shall be attached to this procedure when the procedure is complete.
5.0 PROCEDURE I 5.1 IF in CTS: cold shutdown {ITS: Modes 5, 6, or defueled},
THEN verify the following:
(Otherwisd mark this step as N/A)
- The Steam Generators are drained to a level sufficient to accept AFW flows. A! IM
- The RCS is NOT solid.
NOTE: When operability testing of Train A is NOT required, then N/A Steps 5.2 through 5.33.
5.2 TRAIN A TEST 5.2.1 IF performing Section 5.2, THEN the following auxiliary feedwater pumps with their associated flow paths, are operable as applicable.
(N/A the step that is NOT applicable.)
- a. For two-unit operation:
P-38B, 1P-29, and 2P-29 are operable a PW
- b. For single-unit operation:
P-38B and 1P-29 are operable for Unit 1 OR P-38B and 2P-29 are operable for Unit 2 §Qf -
5.2.2 IF sufficient qualified operators are NOT available on shift to support Step 5.2.3, THEN consider the equipment unavailable per Maintenance Rule AND N/A Step 5.2.3. A?
Page 6 of 53 CONTINUOUS USE
POINT BEACH NUCLEAR PLANT IT 1OA SAFETY RELATED INStERVICE TESTS Revision 11 July 5, 2001 TEST OF ELECTRICALLY-DRIVEN AUXILIARY FEED PUMPS AND VALVES WITH FLOW TO UNIT 1 STEAM GENERATORS (QUARTERLY)
INITIALS INITIALS 5.2.3 Assign a Level 4 Dedicated Operator in the Control Room AND a Level 4 Dedicated Operator in the field per OM 3.26, Use of Dedicated Operators, to perform the restoration steps of Attachment J, if required. (Otherwise mark this step as N/A) y4 I 5.3 Enter a CTS: LCO (ITS: Action Condition) for P-38A.
I (N/A this step if not required for current plant conditions per CTS:
1ý'4 5 7-Technical Specification 15.3.4 (ITS: 3.7.5))
TIME *-'DATE 5 /3 /0-L 5.4 IF an Auxiliary Feedwater Initiation is required during the performance of
!is test, THEN immediately perform Attachment J to recover Train A.
(N/A this step if not required.)
©~
Page 7 of 53 CONTINUOUS USE
POINT BEACH NUCLEAR PLANT IT 10A INSERVICE TESTS SAFETY RELATED Revision 11 July 5, 2001 TEST OF ELECTRICALLY-DRIVEN AUXILIARY FEED PUMPS AND VALVES WITH FLOW TO UNIT 1 STEAM GENERATORS (QUARTERLY)
INITIALS 5.14 Check AF-4007, P-38A AFP Mini-Recirc Control, mini-recirculation valve open.
5.15 Check mini-recirculation flow equal to or greater than 70 gpm on FIT-4050A.
U 5.16 Check the packing glands for excessive leakage or overheating. 1, 5.17 Check pump and motor for unusual noise or overheating.
. ý'T 5.18 WHEN P-38A has run for five-minutes, THEN record the following on Attachment B.
"* PI-4011, Pump Discharge Pressure.
"* PI-4010A, Pump Suction Pressure.
"* FIT-4050A, Mini-Recirculation Flow.
"* Recirculation Flow Vibration Data.
0 Page 12 of 53 CONTINUOUS USE
POINT BEACH NUCLEAR PLANT IT 10A INSERVICE TESTS SAFETY RELATED Revision 11 TEST OF ELECTRICALLY-DRIVEN AUXILIARY FEED July 5, 2001 PUMPS AND VALVES WITH FLOW TO UNIT 1 STEAM GENERATORS (QUARTERLY)
INITIALS INITIALS 5.46 Check AF-4014, P-38B AFP Mini-Recirc Control, mini-recirculation valve open.
5.47 Check mini-recirculation flow equal to or greater than 70 gpm on FIT-4050B.
465 5.48 Check packing glands for excessive leakage or overheating.
5.49 Check the pump and motor for unusual noise or overheating.
5.50 WHEN P-38B has run for five-minutes, THEN record the following data on Attachment F:
"* PI-4018, Pump Discharge Pressure
"* PI-4017A, Pump Suction Pressure
"* FIT-4050B, Mini-Recirculation Flow
- Recirculation Flow Vibration Data 40 ý11 Page 25 of 53 CONTINUOUS USE
POINT BEACH NUCLEAR PLANT IT 10A INSERVICE TESTS SAFETY RELATED Revision 1I TEST OF ELECTRICALLY-DRIVEN AUXILIARY FEED July 5, 2001 PUMPS AND VALVES WITH FLOW TO UNIT I STEAM CWNFPR ATORS (OUARTERLY' REMARKS SECTION: 7-mA; I cat rc-h-r z,ý fer R 1=F-Vo20 o/,,F-YVo2Z Z71F-/e13 2-AlF-/0'--.
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Page 35 of 53 CONTINUOUS USE
POINT BEACH NUCLEAR PLANT IT 10A INSERVICE TESTS SAFETY RELATED Revision 11 TEST OF ELECTRICALLY-DRIVEN AUXILIARY FEED July 5, 2001 PUMPS AND VALVES WITH FLOW TO UNIT 1 STEAM GENERATORS (OUARTERLY)
ATTACHMENT B P-38A, AFW PUMP PERFORMANCE DATA (RECIRCULATION FLOW)
NOTE 1: The data recorded on Attachment B is for information only.
NOTE 2: Vibration points which are shaded must be recorded by the Micro-logger but are NOT required to be transferred to the table. Only points marked A, B, C, D, and E must be transferred to the table and are required for ASME Section XI. See Figure 1 for locations.
Step No. Parameter Measured I Units Reading Acceptance Criteria Initials 5.10.3 PI-4010A, P-38A AFP Suction Pressure psig INA 5.13 PI-4010A, P-38A AFP Suction Pressure psig (. >7 5.18 PI-4011 Pump Discharge Pressure psig *3i N/A 5.18 PI-4010A, P-38A AFP Suction Pressure psig NIA 5.18 FIT-4050A, Mini-Recirc Flow gpm "_79S N/A 5.18 Recirculation Flow Vibration Data INSTRUMENT UNITSREAIANGS P38A 1V ips Note 2 Micro-logger IPS pk C.-
P38A 1H ips Note 2 Micro-logger IPS pk P38A 1H ae Note 2 Micro-logger G env P38A IH ace Note 2 Micro-logger G pk P38A IA ips Note 2 Micro-logger IPS pk P38A 2V ips Note 2 Micro-logger IPS pk _ _
P38A 2H ips Note 2 Micro-logger IPS pk P38A 2H ae Note 2 Micro-logger G env P38A 2H ace Note 2 Micro-logger G pk _
P38A 2A ips Note 2 Micro-logger IPS pk P38A 3V ips Note 2 Micro-logger IPS pk P38A 3H ips Note 2 Micro-logger IPS pk P38A 3H ae Note 2 Micro-logger G env P38A 3H ace Note 2 Micro-logger G pk P38A 4V ips Note 2 Micro-logger IPS pk P38A 4H ips Note 2 Micro-logger IPS pk P38A 4H ae Note 2 Micro-logger G env P38A 4H ace Note 2 Micro-logger G pk P38A 4A ips Note 2 Micro-logger IPS pk Page 39 of 53 CONTINUOUS USE
POINT BEACH NUCLEAR PLANT IT 10A INSERVICE TESTS SAFETY RELATED Revision 11 July 5, 2001 TEST OF ELECTRICALLY-DRIVEN AUXILIARY FEED PUMPS AND VALVES WITH FLOW TO UNIT I STEAM GENERATORS (OUARTERLY)
ATTACHMENT F P-38B, AFW PUMP PERFORMANCE DATA (RECIRCULATION FLOW)
NOTE 1: The data recorded on Attachment F is for information only.
NOTE 2: Vibration points which are shaded must be recorded by the Micro-logger but are NOT required to be transferred to the table. Only points marked A, B, C, D, and E must be transferred to the table and are required for ASME Section XI. See Figure 1 for Locations.
Step No. Parameter Measured Units Reading Acceptance Criteria Initials 5.42.3 PI-4017A, P-38B AFP Suction Pressure psig ' NIA 5.45 PI-4017A, P-38B AFP Suction Pressure Psig "j>7" 5.50 PI-4018 Pump Discharge Pressure psig N/A 5.50 PI-4017A. P-38B AFP Suction Pressure psig N/A 5.50 FIT-4050B, Mini-Recirc Flow gpm "7+/-L4L N/A 5.50 Recirculation Flow Vibration Data INSTRUMENT UNITS READINGS" P38B IVips Note 2 Micro-logger IPS pk P38B IH ips Note 2 Micro-logger IPS pk P38B IH ae Note 2 Micro-logger Genv P38B 1H acc Note 2 Micro-logger G pk P38B 1A ips Note 2 Micro-logger IPS pk P38B 2V ips Note 2 Micro-logger IPS pk P38B 2H ips Note 2 Micro-logger IPS pk P38B 2H ae Note 2 Micro-logger Genv P38B 2H acc Note 2 Micro-logger Gpk N' P38B 2A ips Note 2 Micro-logger IPS pk P38B 3V ips Note 2 Micro-logger IPS pk P38B 3H ips Note 2 Micro-logger IPS pk P38B 3H ae Note 2 Micro-logger Genv P38B 3H acc Note 2 Micro-logger Gpk P38B 4V ips Note 2 Micro-logger IPS pk P38B 4H ips Note 2 Micro-logger IPS pk P38B 4H ae Note 2 Micro-logger G ean P38B 4H acc Note 2 Micro-logger G pk P38B 4A ips Note 2 Micro-logger IPS pk
/
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