Text

Forwards Documentation for Review by NRC to Support Restart Issues as Identified on Unit 2 Startup Commitment List.Items Are Listed
	ML20137P823
Person / Time
Site:	Point Beach
Issue date:	04/01/1997
From:	Dante Johnson; WISCONSIN ELECTRIC POWER CO.
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20137P828	List: ML20137P830; ML20137P844; ML20137P850; ML20137P855; NPL-97-0127, Forwards Documentation for Review by NRC to Support Restart Issues as Identified on Unit 2 Startup Commitment List.Items Are Listed;
References
	NPL-97-0127, NPL-97-127, NUDOCS 9704100022
	Download: ML20137P823 (69)
	v • d • e

" ~~

Wisconsin Electnc POWER COMPANY Point Beoch Nuclear Plant (414) 755-2321 6610 Nuclear Rd.. Two Rheers, WI 54241 NPL 97-0127 l

April 1,1997

- Document Control Desk U. S. NUCLEAR REGULATORY COMMISSION Mail Station Pl-137 Washington, DC 20555

- Ladies / Gentlemen:

DOCKET 50-301 RESTART DOCUMENTATION POINT BEACII NUCLEAR PLANT. UNIT 2 Pursuant to discussions conducted at a January 31,1997, NRC/ Wisconsin Electric senior management meeting, we are enclosing documentation for review by your staff to support restart issues as identified on the Unit 2 Startup Commitment List. The items are:

7: Complete a review of Unit 2 administrative cor.: 'ols implementing or referencing Technical m.

SpeciGeations to ensure Technical Specification requirements are appropriately reDected in the administrative controls.

/

We are enclosing letter NPL 97-0048 dated February 28,1997 detailing our review Endings. Also

)

enclosed are Condition Report (CR) descriptions for 97-0723,97-0724,97-0725,97-0726,97-0727, 97-0746,97-0766 and 97-0831 that were issued based on our findings. The independent review results are also enclosed.

15: Review 20% of the work orders performed since January 1,1995 on Unit 2 or common PSA safety signincant systems (AFW, SW, EDG, IA,4.16 kV, gas turbine, and CCW) to verify adequate PMT was performed to ensure system / component safety function.

We are enclosing Qua ity Assurance Program Surveillance Report S-P-97-01 dated March 1.

1997 that was performed January 20-February 10,1997. Also enclosed are Quality Condition Report (QCR) descriptions for 97-0002,97-0005,97-0006,97-0007,97-0008,97-0009,97-0010,97-0011,97-0012, and 97-0013 that were is ued based on our findings. The independent review results are also enclosed.

09009 9704100022 970401 P

PDR ADOCK 05000301.

P PDR i'

{gfEfh@

omn-a a, c--

NPI) 97-0127

. April 1,' 1997 :

. Page 2 '

' #16: Complete all Unit 2 Maintenance Rule-related work order post-work, pre-PMT revie' s prior to the w

approach to criticality.

We are enclosing the independer.t review results.

33: implement interim improvements for the 10 CFR 50.59 process to require that all screenings be

- either authored or reviewed by a member of the multi-disciplinary review team.

We are enclosing N.P 10.3.1, Revision 5, dated February 14,1997, Safety Evaluation Fonn PDF-1515, l

training records and a listing of qualified in-line review team members dated March 17,1997. We are j

also enclosing the independent review results.

'#37: Include return to service testing in the plant schedule, both outage and non-outage.

! We are enclosing examples of PMT added to the Major item Work List, NP 8.1.1, Revision 4, dated j

' January 24,1997. We are also enclosing the independent review results.

1 i

41: Perform Modification 92-141 that relocates the RHR flow control valve controllers on 2C-03 for human factoring.

i We are' enclosing Work Order 9605772, MWR Work Plan MR 92-141, and MR 92-141. We are also enclosing the independent review results.

?

70: ' Install a new level control system for the brine tank (T-118) per Modification 92-008*Q.

3 l

i

.We are enclosing Work Order 9701182, IWP 92-008*Q-02 and Engineering Change Request 97-0008.

. We are also enclosing the independent review results.

j

74: 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.

l We are enclosing Lesson Plan TRPR 33.0, Revision 0. We are also enclosing the independent review l

resultsi l

l l

NPL 97-0127-April 1,1997 Page 3 j

Also enclosed is the Unit 2 Startup Commitment List dated March 27,1997.

Sincerely, hN sb-Douglas F. Johnson Manager-Regulatory Services & Licensing MBK/hds Enclosures cc:

NRC Regional Administrr. tor i

I PAGE 1

vw, i

-ACTION ITEM STATUS REPORT 03/31/97-Responsible Person:

l**** kid: U2R22 RESTART Urgency: DONE i*:Tr Work Priority:

99

Action Number:

7 Activity Pending is: DONE-ASSOCIATED WITH A COMMITMENT I----------TITLE AND TASK DESCRIPTION------------------------

l Unit 2 Refueling 22 Startup Commitments fPriortoleavingcoldshutdown, the review of Unit 2 administrative controls implementing or referencing Technical Specifications to ensure TS requirements are. appropriately reflected via administrative controls shall be included in appropriate documents.

ion ******

,Sourqe Record:----------DATES- /10/97

- - - - Evaluation *********

- - - - Correct 01 jCommitment:

Eval Due:

Corr Act Due: 03 97

ActLon Create: 01 10 97 Orig Eval Due:

Orig CA Due:

02 97

Act: .on Closed: 03 31 97 Eval Done:

Corr Act Done:02 97

----------PEOPLE----------------------------------------

Responsible for Overall Action:

SI Responsible for Current Pending Activity:

Issug Manager:

Initiator:

Punchlist Administrator:

.........-UPDATE------------

(01/29/97 My planned course of action is as follows: 1)

Obtain existing cross-references which relate TS surveillances/LCOs to plant procedures. 2)

Annotate the procedure number on the associated surveillance /LCO,in the Technical Specifications 3)

Provide initial cross-reference information to contractor and NPBU personnel to verify accuracy of information and perform technical review of procedure adequacy in imolementing associated Technical Specification. 4)

Perform electronic t

ocedures for references to Technical Specifications.

t search of all plant pr/ Procedure cross-reference and oerform review in #3 5)

Further refine TS cross-reference,de close-out documentation which includes the TS/ procedure above. 6 Provi a list of discrepancies, and recommendations.

NPBU personnel sug/97--Several existing cross-references were obtained via Status as of 1/29 gestions All applicable information from these cross-references has been incorporated into " master" cross-reference.

The technical review is in progress to verify this information.

An electronic search of all plant procedures with references to the t

echnical Specifications has been comoleted.

648 procedures were i

dentifi d.

All of these procedures have been reviewed and applicable 9

nformation annotaged on the master cross-reference.

Technical review nas commenced on this information.

l Currently 5urve11Iances which are still without an identifiedto identify implementing procedures l

I am going back and trying for LQ0e7 i

administrative control which implements them.

j I estimate that I am approxmately 25% com l with

]

thefeglingthatthetechnicalreviewwilSetewiththisactionitembe extremely arduous and time consuming.

]

(01/31/97 This item was discussed at the NPBU Senior Team meeting yegterday.

Due to the fact that seperate thorough technical reviews are i'

bainq ctaduct d on procedures to complete e&her U2 sk,xt-up items in paraILel with this review, this review will only entail an administrative verif; cation Qhat all TS s urveillance frequencies and associated LCOs are l

correctly indicated in NPBU procedures and other administrative controls.

(02/05/97 Requested Due Date:

02/25/97 This extensign is requested due to my less than/11/97 to 02/25/97 expected available time to

-(02/06/97 Changed the Due Date from:

02 devote to this project because of greater than expected routine, NRC-required regulato n work.

This administrative review has required 1

more specific technical knowledge than originally anticipated.

Therefore J

necessa n suppor$ from procedure " owners" may cause further delays in the, completi6n ot tais project.

i

=

ACTION ITEM STATUS REPORT PAGE-2 03/31/97

~(02/24/97 Requested Due Date:

03/19/97 (02/24 Changed the Due Date from:

02/25/97 to 03/19/97 Additio/97nal time needed to evaluate apparent discrepancies and match LCOs to surveillances.

(02/24/97

). Changed the Due Date from:

03/19/97 to 03/19/97

.(02/28/97-Passed to for acceptance of work.

(02/28/97

) Passed to.

for-Verification.

-M evaluation of PBNP Unit 1 and 2 aoministrative controls for-im leuentation of Technical Specifications was completed on February 28, 19 and forwarded to via NFL 97-004B, Condition reports wi

,be written on 14 possioie procedural inadequacies and other adm nistrative deficiencies.

This item can be closed.

(03/28/97.

Passed tc

. for Final Close Out.

Collected documentation and reviewed same. -This item is ready for closecut.

(03

) PLA Closure of Item.

Enfo/31/97 Conference Item #3 also addresses this issue.

NPL 97-0048

~

rcement 1997 addresses this issue.

CRs 97-0723, 97-0724, dated Februan 28,97-0727, 97-0746 97-0766, and 97-0831 were written 97-0725, 97-0726, documenting items for future' follow,up.

REFERENCES--------------------------------------------------

PBL-97-0033 IR 96-008 NPL 97-0048 CR 97-0723 CR 97-0724 CR 97-0725 CR 97-0726 CR 97-0727 CR 97-0746 CR 97-0766 CR 97-0833

MISCELLANEOUS----------------------

Originating Agency:

S stem:

XX NRC Open Item Number:

N C Status:

Related Outages:

U2R22 Engineering Work Type: None Specified Person Hours:

Original EsQimate =

Current Estimate

=

Actual Hours

=

l.3

}'

f I

i l

f 9

m

INTERNAL CORRESPONDENCE NPL 97-0048 To:

From:

Date: February 28,1997 subject: EVALUATION OF PBNP ADMfNISTRATIVE CONTROLS IMPLEMENTATION OF TECHNICAL SPECIFICATIONS Copy To:

File Attached is our evaluation of Enforcement Conference / Unit 2 Restart Commitment #7.

" Complete a review of administrative controls implementing or referencing Technical Specifications to ensure Technical Specification requirements are appropriately reflected in the administrative controls." This evaluation was conducted for Units I and 2 to ensure that all limiting conditions for operation (LCOs)in Technical Specifications Section 15.3 and surveillances in Technical Specifications Section 15.4 are implemented by plant procedures.

1 Approximately 700 plant procedures were reviewed. Although the evaluation consisted of an administrative review to ensure that Technical Specifications LCOs and surveillances are imp!emented at the required frequencies, a limited technical adequacy review was also conducted when possible. However, it is recommended that a complete technical adequacy review be conducted on a sample of these procedures. This evaluation did not include a review of procedure implementation of Action statements for LCOs or a review of procedure. call-ups in the CHAMPS systemc-During the course of this review, several common themes emerged:

i

1. Technical Specifications surveillances are being conducted a* their required frequencies with the exception of 14 possible procedural inadequacies. Several other administrative deficiencies were also idendfied.

2. The tiers of administra:ive procedures reiterating Technical Specifications requirements are rife with inaccuracie'. and in:onsistencies.

3. Specific references to affected Technical Specifications is sparse. When references to affected Te~chnical Sm.!fications were incLad, many times tndy were incorrect.

4. Citation of the affected Technical Specifications requirement satisfied by implementing procedures is highly variable. Some procedures properly cite the specific requirement while others may only make casual reference to a major Technical Specifications sub-section.

_ s February 28,1997 Page 2 This evaluation completes NUTRK action items U2R22 Restart #7 and NRC 96EC #3.

' Condition Reports will be initiated on the findings documented in the " Comments" section of

- this evaluation.

I i

'i

)

l t

i a

a e

MM49EN O a

[

a

y PBNP Technical Specifications implementation in Administrative Controls Closecut of NUTRK Action items U2R22 Restart #7 and NRC 96EC #3 TS L 20 Description TS Surveillance implementing Procedure Comments Cross Reference 15.31 A 1 a When the reactor is crdical, at least 1 RCP shah be in ARB CO2 F4-4 steps 6 3 & 6 4. OP 18 step 3 8,3 9 operation OP-1C step 21.1 OP-48 step 31 15 31.A 1 b When the reactor is subcnhcal and RCS temp > 350*F. at CL-1D step 31. RESP 3.1 steps 3 5 6,5141 RESP 3.1 step 5141 states further TS.

least 1 RCP shall be in operation invoke the test excephon to ttus LCO.

restrictions without provtfing specific reference (no ddutacns, core cutlet 10*F <

15 31 A.1 c At least 1 RCP or RHR system shall be in operation when OP-1 A step 2 2 4,2 5 3. 417 3. OP-1B step 33 saturation, trip tweakers opea) reducing Boron conc.

15 31 A 2 a One Steam Generator sha!! be operatde when RCS temp >

15 4 2 A 350*F CL-1 A step 12 Ct -10 step S 1 15 31 A 3 a Components for decay heat removal capatality at RCS OP-1 A note for step 4 6 5. CL-1D steps 1.1 t 6 temperatures between 140 and 350*F

21. 2 22, IT-530 & IT-531 (Urut 1) and iT-535 & IT-536 (Una 2) steps 3 2 system leak test PRECAUTIONS

& tluiT AflONS for decay heat removal capabihty 1531A3b Components for decay heat removal capatahty at RCS OP-4D pat 1 step 31. CL-1D steps 1.1.16 RMP temperatures <140*F 118 steps 2 2.1 & 2.2.2 (1St 852A(B) vatve operator maintenance references this LCO) TS-30 step 2.2 and TS-31 step 2 2 lea's test PRECAUitONS &

t IM11 AllONS for decay heat removal capabd ty, (T-531 (Unit 1) and iT-536 (Unit 2) steps 3 2 system leak test PRECAUllONS & L tutI ATIONS for decay beat removal capabthty 15 31 A 4 a At least one pressurizer safety valve operable when reactor Table 15 41-2 #11 CL-10 steps 12,2 2,3 3 vessel head is on 15 31.A 4 b Both pressuruer safety valves operable when reactor is Table 15 41-2 #11 critical CL-1 A step 1.3

~

15 31 A 5 a Two PORVs and their associated block valves shall be Table 15 41-1 #33. #34, #35 CL-t A step 13 operable Table 15 41-2 #21a, #21b 15 31 A 6 Pressuruer shall be operable with 100 KW of heaters Table 15 4.1-2 #30 CL-10 step 4 2 CL-1 A step 1.3 & 18. TS-43 heater avadable, water level between 10 and 95%, and at least one Table 15 41-2 #9a

,3 bank of heaters shall be supphed from an emergency bus group quarterly energy input test, RESP 31 step 5 8 power supply measures heater power 15 31 A.7 a At least one Reactor Coolant Gas Vent System path shau be CL-1 A step 19,CL-1D steps 2 4. 3 5,4 3 operable from both the reactor head and the pressurtzer 15 31 B 1 RCS temperature and pressure hmet curves OP-1 A steps 2 4 3. 2 410,2 412 01-105, step 21 15 31 B 1 a iteatup 5100*F in any 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 01-105, step 21 15.31 B 1 b Cooldown 5100*F in.,ny 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 01-105, step 21 15 31 B.1 c

' Average temperature change of510*F per hour during OP-1 A step 2 411 hydros & leak testing 1

Ji@h v

.um s.

TS LCO Description TS Surveillance implementinD Procedure Cross Reference Comments 1531B2 Steam gerwrator p essure $_200 pssg af SG vecsel shes tem

< 70*F p

04112 A/B step 2.1 Q 70*F to pressurize) 15 31.B 3 a

~ Pressurizer temperature heatup 5100'F in any 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , OP-1 A step 2 4 2 (Adnun kmt) rW < 200*f c i any 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 15 3,1 B.3 b.

Spray temperature wettun 320 F of pressunzer temp t

T S-43 heater group quarterly energy input test notes this Isautation 153184 Reactor vesset pressure temperature curves ' e4RC 60d prior to experation OP-1 A step 2 4 8 Reactor coolant spectre activity y 1.0 merocurie per gram Currentty not tracked Of covers specimen 15.31.C.1 Tatde 15 41-2 #1 remoral Dose Equivalent 1-131 CL-1D steps 3 9,4 7 15 31 C 2 Reactor coolant sptfac actMty 5100/E.Amuries per Tatde 15 41-2 #1 CL-1 A step 1.4, CL-1D steps 3 9,4 7. CAMP-406 (E gram 15,31.D.1 RCS leakage $ Igpm bar deternunation)

TatAe 15 41-2 #16 IS 31 D 2 RCS teakage 510gpm 0155 step 31. CL-10 steps 2 5,3 6,4 4 Tatde 15 41-2 #16 Oi 55 step 3 2, CL-1 A step 15 CL-10 steps 2 5 15 31 D 3 Leakage evais per :S 31 D 2 to assure < 10CFR20 hmas to 36.44 TatAe 15.41-2 #16 the pubhc CL-1 A step 1.5, CL-1D steps 2 5,3 6,4 4 Tivs TS, anhough empicit in the text of these 1531D4 Pnmary to secondary leakage s 500gpd Tatde 15 41 2 #16 steps is not dwectly referenced RMSASRB Cl RE-219 RMSASRB Cl RE-222 RMSASRB Cl HE-225 RMSASRB Cl RE-231 RMSASRB Cl RE-232 153105 tJon asotatatAe RCS ieakage CL-ID steps 27,3 7,4 5 TatAe 15 41-2 #16 No reactor restort u.it:1 leak is repaired CL-10 steps 2 0,3 8,4 6 15 31.D 6 Table 15.41-2 #16 OM-41.1 step 4 6 15 31 D 7 Two reactor coolant leak detection systems M operattun ECL-5 step 31 when reactor is in power operahon Table 15 41-2 #16 RMSASRB Cl RE 211 RMSASRB Cl RE-212 RMSASRB Cl RE-305 shoukt also refer to IS31D8 Secondary can' ant gross radioactivity shan be monitored

- 15 31 D 7 Table 15.41-2 #16 contu=Wy by an air ejector gas morutor. Secondary RMSASRB CI RE-215 coolant gross radioactivdy shall be measured weekly.

RMSASRB Cl RE 225 Secc..o cs coolant Cross radioactMty shall be measured CL-ID steps 1.7,2 8,3.10,4 8, PBNP 8 41 Ady it av ejector not operatna 15 3.1 E.1 The concentration of oxygen in the reactor coolant shaB be 5 TatAe 15 4.1-2#1 01 ppm OP-1 A step 4 7, CL-1D step 2 9 < 100 ppb, NP 3 2.2 I

15 31 E 2 The concentrabon of chlorkie in the reactor coolant shan be 5 fatAe 15 4.1-2#1 step 7.1(a) (general reference to 15 31 E -info only) 015 ppm CL-1D step 2.10 < 150 ppb, OP-1 A step 4 6.7 refs i

NP 3 2 2 NP 3 2 2 step 7.1(a)(general reference to i

1531E3 The concentration of fluoride in the reactor m'+nt shan be s 15 31 E -info only)

Table 15 41-221 015 ppm CL-1D step 2.10 < 150 ppb, OP-1 A step 4 6.7 refs NP 3 2.2, f 4P 3 2.2 step 7.1(a){ general reference to 15.31.F,1 Reactor shall not be mada crrical when the moderator RESP 41 step 5.17 measures the HZP MTC and 15 31 E -info only) i 4

l p

f

.

TS LCO Description TS Surveillance implementing Procedure Comments Cross Reference temperature coeffuent is more postrve than 5 pcneF directs admalestrative bmd of Bank D wahdrawat to maintain < +5 pctrrF CL-1 A step 1.6 MTC5 +5pcm,"F, RESP-4.1 step 611 IS 31.F.2 Reactor power shd rx4 exceed 70% of Rated Power if the OP-1C step 2 3.2, RESP-41 step 518. ROD 8 5, moderator tempereture coefficient is posalve 15 31.F.3 Durmg crncaldy approach, at least 1 cps a:tributable to RESP-41 step 415 (sr gicpm) if RESP-4.1 is not controlhng the startup.

neutrons shat register on a narrow range source range PJi this requirement is not cated od in the.

controahna procedure (OP-18 step 410) 15 3 I F.4 Reactor core cracaldy curve Fig 15 31-1 CL-1 A step 1.7 OP-1B step 4 6 15 31 F.5 Reactor maintained subcritical by at least 1% AK/K unts CL-1D step 3 31 TS referenced in this step of CL-1D should norrnal water level is estabhshed m p;essurtter OP-1B step 4 6 be 15.31 F 5 red 15.31.F,4 15 3.1.G 1 Tavg < 578-F Table 15 41-184 ARB CO4 3-10 & 3-11 Alarm @ 575 Deviation at +3/*5 STPT 6 2 15 31.G 2 a Und 1 RCS pressunzer pressure sha9 be maantained a 2205 Table 15 41-1s7 tJot in OP, AOP, or BG AOP psig dunng operahon at 2250 psia of a 1955 psig dunng operaton at 2000 mm 15 3.1 G 2.b und 2 RCS pressurtzer pressure sha5 be matrdained 11955 Table 15.41-1s7 f4ot m OP, AOP, or BG AOP pseg during operatsnn at 2000 psig 15 31 G 3 a Und ? RCS raw m, asured flow 1181,800 gpm Table 15 41-1s5 RESP 6 2 precision measurement of RCS flow

~

(RESP 6 3 performed when 6 2 is not Nactcal) 15 31 G 3 b und 2 RCS rawincasured ikw t 174.000 gpm Table 15 41-185 RESP 6 2 prectsion measurement of RCS flow Ffgure 15 31-2 C~% tmda (RESP 6 3 performed when 6 2 is not practical)01-105 Figure 15 31-5 Dose equivalerst 1-131 vs % Power Table 15 41-281 Referenced in CL-1 A steps 1.4,3 6 15 3 2 A When fuel is in the reactor, there shall be at least I flow path Table 15 41-1 #21 CL-10 steps 1.4,1.0,2.12,213,311,3.12 to the core for boric aculinfection 15 3 2 B 1 Reactor shall not bGaken crescal unless a minimum of 2 Table 15 4.1-1 #23 CL-1 A step 10 31.CL-tD step 213,312,410

(

chargtng pumps los that reactor are operat9e Table 15 41-2 #31 15 3 2 B 2 Reactor shall not be taken crdeal unless 2 flowpaths from Table 15.41-1 #21 CL-1 A step 10 3 2,10 3 3, CL-1 D step 214,313, BASTS or RWST operable RMP 29C step 41.4, RMP 290 step 412, RMP 29E step 41.2 15 3 2 B 3 a if retying on BAST paths, then one BA transfer pump Table 15 41-1 #21 operable per flowpath w/ one of the BAST fkapaths kned up CL-1 A step 10 3 3. CL-1D step 2.151,3141 to supply apphcable reactor.

15 3 2.B.3 b if relying ec 53AST paths, then BA concentratten,iiWimm.im Tatile 1541-1#22 CL-1 A step to 3 3, CL-10 step 215 2. 314 2 NP volume and solution temperature meet Table 15 3 2-1 3 2 2 step 8 5 (general reference to 15 32 -info onM 15 3 2.C.1 A second reactor shaN not be taken critical unless a Table 15 4.1-1 #23 CL-1 A step 9 31 munmum of 2 charging pcmps for that reactor are operable Table 15 41-2 #31 1532C2 A second reactor shan not be taken critcal unless 2 Tatde 15 41-1 #21 CL-1 A step 9 3 2 CL-1D steps 2.14,313 flowpaths from BAST s or RWST operable to each RCS 3

L m

TS LCO Description TS Lurveillance implementing Procedure Comments Cross Reference 15 3 2.C.3 a if retyeg on BAST paths, then one BA transfer pump Table 15 41-1 #21 CL-1 A step 9.3 3, CL-1D steps,2.15 t,3.14.1 cperable per flowpath wf one of the BAST ikmpaths lined up to supply appricable reactor.

15 3 2 C.3 b if relymg on BAST paths,then BAST wi.cntration.

Table 15 41-1 #22 CL-1 A step 9 3.3, CL-1D steps 2.15.2,3.14 2 movmum vobme and solubon temperature meet Table 1532 '

Table 15 3 2-1 BAST concentration, rrmwnum volume and soluton Table 15 41-1 #22 CL-1 A steps 9.3 3,10.3 3 temperature Table 15 41-2 #4..#20 Of-99A step 3 4 5 U

15.3 3 A.1 a A sector shat not be made critical unless the RWST Table 15 4.1-2 83 CL-1 A step 2.1.1, CL-1D step 315 7

contains ? 275,000 gal of a 2000 rpm boron conc water 15 3 3 A 1 b A reactor shad not be made craical unless each accumulator Table 15 41-1 #18 CL-1 A step 2.1.2 is 3 00 psig and between 1100 ft* and 1136 ft* 12000 ppm Table 15 4.1-2 #6 7

boron cone water 4

13 3.3 A.1 c A reactor shau not be made cracal unless 2 SI pumps are 1545 CL-1 A step 2.1.3

.i operable I5.3 3 A.1 d A reactor shau not be made crRical unless 2 RHR pumps are 1545 CL-1 A step 2.1.4, CL-10 step 317 operable 13 3 3 A 1.e A reactor shad not be made crdcal unless 2 RHR heat.

1545 CL-1 A step 2.1.5 CL-10 step 317 exchangers are operable 15 3.3 A.1 i A reactor shat not be made cracal unless isolation valves of 1545 CL-1D step 3.161 i

the high head SI system are open 15 3 3 A.1 g A reactor shad not be mai e critical unless aR va!ves, 1545 CL-1 A step 21.6 CL-1D step 316.1,317 irdertocks, and piping associated wth the above systems are operatde 15 3 3 A 1 h A reactor shau not re made critical unless AC power source 1545 OP-1 A step 414 6, CL-1D step 316.1 removed from MOV-841 A & B wth valves open at > 1000 1

psig 15.3 3 B.1 a A reactor shan not be made crdcal unless the spray additive Table 15 41-2 #5 CL-1 A step 2.2.1 CL-1D step 218,3.18 tank has > 2675 gal of 30% NaOH solution 1545

ti 15.3.3 B 1.b A reactor shan not be made critcal unless 2 cont== inst 1545 CL-1/. step 2 2.3 CL-1D step 2.19,3.19 i

spray pumps are operable 4

15.3 ? B.1 c A e eactor shat not be made crdcal unless 4 accident fan 1545 CL-1 A step 2.2.4 CL-1D step 2.20,3.20. TS 33 cooler units are oparable containment accident rocirculation fan cooler monthly test 15 3 3 B 1 d A reactor shall not be made craical unless at valves and 1545 CL-1D step 2.21,3 21 ptpang associated veith the above systems and required to function are operable

)

15 3 3 C.1 a One reactor shall not be made crdical unless 2 wn,xivent CL-1 A step 10.1.1, CL 10 step 16,2.22,3 22 Single una cooling pumps assigned to that unit are operable 15 3 3 C.1 b One reactor shau not be made critical unless either the CCW CL-1 A step 10.1.2, CL 1D step 1.6,2 22,3 22 Single unit heat exchanger associated with the Unit together with 1 of the shared spare heat exchangers are operable or 2 shared neat exchangers are operable 15 3 3 C 1 c One reactor shau not be made cracal unless at valves, CL-1 A step 101.3 CL-1D step 1.6,2.22,3.22

[

St#gle urut mierlocks and piping associated with the above components, 4

. l

?

. -.. - - _. -.. -..,.....~

.,..,.. ~~,

.w,

-~

TS LCO Description TS Surveillance implementing Procedure Comments Cross Reference and requred for the funcboning of the system dunng acudent condttiona are operable 15 3 ; C.1.a Two Both reactors shan not be made crdical unless 3 miw.--a CL-1 A step 91.1 CL-10 step 1.6,2.22,3 22 und operat:on cooling pumps are operable 15 3 3 C.1.b Two Both reactora shan not be made crtcal unless 3 wgonent CL-1 A s'ep 9.1.2 CL-1D step 16,2 22,3.22 und operation coohng heat exchangers are operaNe 15 3 3 C.1 c Two Both reactors shat not be made criteal unless all valves.

CL-1 A step 913 CL-10 step 16,2.22,3 22 und operation rderlocks and piping associated wth the above components, and requ: red for the functioning of the system during accident conditions are operable 15.3 3 0.1.a Nedher reactor that be made or mainuuned crdral unless 4 Table 15 41-2 #15 CL-1 A step 2.31, RMP 29F step 41.2, RMP 23A service water pumps are operable,2 from each train step 2 4 5 15.3 3 D.1 b Nedher reactor shas be made or maintained cracai unless au Table 15 41-2 #15 CL-1D step 4 21, CL-1 A step 2.3 2 valves, interiocks end ptpang associated wdh the above cornponents, and required for the function ng of the system during accident ccnddions are operable 15.3 4 A.1 When the reactor coolant is heated above 350 F the reactor Table 15 41-2 #12 CL-1 A step 31 CL-10 step 3 24 shau not be taken crdical unless t 8 main steam safety vatves are available 13 3 4 A 2 a Two Unit Operatton - When the reactor coolant is heated 15 4 S CL-1 A step 9 2, CL-10 steps 3 25,4 23 above 350*F the reactor shan not be taken crdical unless a8 4 AFW pumps wdh their associate flow paths and essential instrumentation are operable 15 3 4 A 2 b Single und Operahnn - When the reactor coolant is heated 1548 CL-1 A step 10 2,CL-1D steps 3 2d,4 23 above 350*F tae reactor shad not be taken crdical unless both motor drwen and the turbine dnven AFW pumps with their associate flow paths and essentialInstrumentation are operable 15 3 4 A 3 -

When the reactor coofant is heated above 350*F the reactor Table 15 4.1-1#24 CL-1 A step 3 2 CL-10 step 3.26,4 24 shall not be taken entical unless a 13,000 ga!!ons of water Table 15 4.1-2#15 01-62 A/B step 2 3 per operating unit in the CSTs and Lake water available via the SW system 15 3 4 A 4 When the reactor coolant is heated above 350*F the reactor Table 15.41-1#24 CL-1 A step 3 4 CL-10 step 3 26,4 24 shan not be taken crihcal unless system valves and piping Table 15.41-2815 requtred to function dunng accident condt*nons directly associated wah the above components are operatie 15 3 4'A 5 When the reactor coolant is heated above 350*F the reactor Tab e 15 4.1-2 #28 CL-1 A step 3 5, CL-10 step 2 42 shalt not be taken crdical unless both atmospheric dump itnes are operable 15.3 4 B The lodine-13I actsvdy on the secorwtry side of the steam Table 15 41-2 #8 CL-1 A step 3 6 C1 -10 step 3.27,4 25 generator shaB not exceed 12 pCttec 15 3 4 D The main steam stop valves (MS-2017 & 2018) and the non-1547 CL-1 A step 3 4 CL-1D step 2 43 return check valves ( MS-2017A & 2018A) shau be operable IS34E lThe crossover steam dump system is operable Table 15 41-2 #29 OP-1C step 2.1.4, OP-2A step 21.2 TS-41(Unit 1)

]

& TS-42 (Und 2) crossover steam dump qua.terty 5

m

=

m.

.. t

F y

n 2

L v

TS LCO -

Description

- TS Surveillance implementing Procedure -

Comments -

Cross Reference test 15 8 4 F.

Dunng power cperatm, at least one of the turtune overspeed Table 15 41-1842 TS-3/4 protecten systems that inp the turtane stop valves or shut

?

3 the turbine governor alves shaR be operable i

15.3 4.G Turtune Stop and Govemor Valve opereaGy Table 15 41-2 #18

^

15 3 5 A -

ESF anniation instns.ie setting hmds per Tabte 15 3 5-1 STPT 2.0 15358 Reactor Trip, Safeguards Actuaton, Containment isniahon CL-1 A step 5 6 7 L COs and Actons Tables 15 3 5-2 thru 4 15 3 5 C._

Reactor Trip. Safeguards Actuation. Conta5viw-4 isolaten CL-1 A step 5 6.7 Actor:s Tabies 15 3 5-2 thru 4 1535D Post Accsdent Monnonng LCOs & Actions Table 15.3 Sr5 13.3 6 A.1 Containment integrd/ shan be maintained whert (1) a core is CL-1D step 2 24 Reference in CL-1D shoukt be 15.3 6 A.1 mstaaed unless reactor is in the CSD conddson (2) the rather than 15 6 3 A a

_[

reactor vessel head is removed unless the reactor is m the l

refuew) cond4.on i

15.3 6 A.1 b :

Containment isolation valves (except Purge) - each Table 15 41-2#13 CL-1D step 2 24. OM 3 26 step 3 6 use of dedicated CL-10 step 2.24 imphes comphance with j

containmere penetration must be operable to satisfy 154282 operator as subshtute for remote cperaton of

,15 3 6 A 1 b contamment integrdy containment isolation valves 15 3 6 A.1 c Containment Purge Supply & Exhaust valves shan be locked Table 15 419 #23 CL-1D step 2.24, OM 3 26 step 4 2.3 use of CL-1D step 2.24 emphes compliance with closed unless the reactor is in CSD or Refuel conditon dedicated operator as substaute for remote operation 15.3 6.A 1 c j

of contamment isolation valves 15 3 6 A.1 d Both containment airlocks shan be operable 1544i CL-1D step 2.24. OM 3 26 step 4 2.3 use of.

CL-1D step 2 24 rnphes comphance with dedicated operator as substdute for remote operation 15.3 6 A.1 d I

of containment isolation 15363.1 Contamment intema' Pressure range frorn -2 0 psig to +3 Tabte 15 41 1(27)

CL-1 A step 7.2 CL-1D step 4 28,

Safeguards Staft Log (PDF-2036).

t 1

PSKI acceptance crderia -1 to +2 psig '

f 15.3 6 C Positive reacttvity changes shall not be made by rod dnve OP-1 A step 2.1.5 motion when containment irdegrdy is not iritad 1536O Posdive reactwily chamjes shau not be made by baron OP-1 A step 2 5 2 dilubon when containment integrdy is not in tact unless boron concentration es mamtained > 1800 ppm 15.3 6 E Containment structural integaty snan be maintained in 15441,15.4411

?

accordance wdh the survedlance craena I Containment Leakage Testing Prioram and 15 4 411 15 3.7A1.a fleither one or both of the reactors shan be made crtlical CL-1 A steps 9 41,10 4 la CL-1 D step 4 29 CL-10 step 4 29 merely references CL-1 A f

unless a 2 345KV transmission lines are in service -

15.3 7 A.1 b Nedner one or both of the reactors shan be made crdical CL-1 A steps 9 4 2.10 4 tb

.t unless the 345/13 8 KV and the 13 8/4.16 KV station

+

a suithary transformers for the unit.

15 3 7 A.1.c Nedher one or both of the reacters sha5 be made crdical CL 1 A steps 9 4 3.10 41c unless 4l60 Volt unit supply busses A03 & A04 for the und i

are energtred from normal supply l

15.3 7.A.1.d Neither one or both of the reactors shall be made crdical CL-1 A steps 9 4 4,10 41d unless both unit's B03/B04 bus tie-breakers are open w/

{

i i

4 6

w d

i f

A

-.~. -- --

.v..

..._.,,,_.a.

,._- r..n,-

,-r-

TOLCO Description TS Surveillance implementing Procedure Comments Cross Reference controlre, d

15 3 7A1 e Nether one or both of the reactors shan be made cracal Table 15 41-2 #17 CL-1 A steps 9 4 6,10 4 If unless 11,000 galin each tant being rehed upon to suppty any coerable emergency DG(s) 113 7 A.1_f Nedher one or boe,tf the reactors shau be made craical 15.4 6 B CL-1 A steps 9 4 7,10 4.1g unless 4 of 5 safety-related station batteries and all 4 main DC distrbutscn systems operable 13 3 7 A 1 g Nedher one or both of the reactors shall be made crtral 15.4 6 B CL-1 A steps 9 4 8,10 4 th unless 4 battery charges operable w/ one carrytog load on each main DC bus D01, D02 D03 & D04 15.3 7 A 1 h Nedher one or bott; of the reactors shan be made crax:al Table 15 41-2 #26 CL-1 A steps 9 4 9,10 416 unless 120 VAC vital instrument busses YO1. YO2, YO3, g

YO4, Y101, Y102, Y103, and Y104 are energtred from a safety related trwerter t5.3 7 A.) s For both cf the reactors to be made critical normal and CL-1 A step 9 4 3 standby errergency power to m3 4160/480 Volt safeguards busses shas be operatde and energtred from thee normal supply 15 3 7A1 j For Umt 1 to be rnade crdtcal normat and standby emergency CL-1 A 10 41c power to the 4160/480 Volt safeguards busses und 1 A05/B03, Und 1 Abu/B04 and UnA 2 A06/B04 shall be operable and ene s, Jef from tnair normal supply 15 3 7 A.1.k For Und 2 to be made crdica! normat and standby emergency CL-1 A 10 4 tc power to the 4160/430 Voit safeguards busses und 2 A05/B03, Und 2 AC'i/B04 and Unit 1 A05/B03 shan be operable and energtred from their normai supply 15381 Dunng refueling operatens the equipment hatch shan be RP-1B step 3 6 (partial),

closed and the personnellocks shat be capable of being RP-1 A Att A,B,C closed A temporary door on the outside of the personnel lock shall be in place whenever both doors are open 13382 During refuehng oputxans ead levels in fuel handling areas Table 15 41-1#36 RP-1 A step 31 and the containment and spent fuel pool sha8 be contmuousty montored 15383 During refuehng operations subctdical neutron flux shai! be RP-1 A Att A, B f AuditAe}

continuously mondor-d by at least 2 neutron mondors, each RP-1C step 4 2,4 8,4 9 wah continuous visualindication in the control room and one with audible indicathn in the containment whenever core geometry is being changed. When not being changed, one morutor shaR be in service

=

15384 During refuehng operations at least 1 RHR Icop in operation Table 15.41-1#33 RP-1 A Att A, D 15385 Dunng refuehng operations during head removal and loading Table 15 41-2 #2 REl-19 of unloading core, a 1800 ppm boron in the primary coolant RP-1 A steps 311,4 7 system RP-1C step 416 15386 During refueling operations direct communication between RP-1 A Att A control room and containment cperating floor when core 7

~

a, TG LCO Description T,S Surveillance implerlienting Procedure

- Comments

. Cross Reference geometry changes are taking place I

15357 During refuehng operations Contamment purge and exhaust RP-1C step 31.2,4 2, RMSASRB Ct RE-212, RP-shat be operatde and verified operable within 4 days prior to 18 step 3.5 and once per 7 days during refuehng operatens (manual inshation & hsghlad indtahon) 11310 A.1 When the reactor as craicat, the shutdown banks shall be OP 1B step 5 4 fufy w!!hdrawn 15 3.10 A.2 When the reactor is cnt cal..the control banks shaR be ARB C04-1 A1-8 to i t. Operator response inserted no further than shown on Fig 15310-1 15.3.10 A 3 Shutdown margin shall exceed value shown on Ftg.15 3.10-CL-1D step 3 30. OP-3B step 2 8. OP-4A step 2.1.1 2 ftom 350'F to fut power 15 3.10 A.4 Shutdown margen of at least 1% ok/k when temperature is <

CL-10 step 1.5,2.11 350*F 15 3.10 A 5 During approach to erdecahty, the crtical rod posthon shall Ct.-10 step 4 35 not be lower than the tnserten kmd for 0 power OP-1B step 3 3 15 310 B.1 a Hot channel factor bmits RdSP 61 step 61.1 references 15 3 to B.1 a & b, HEl 13 0 step 3 2c references action statements of 15 3 to B.1.

15 3.10 B.1 b Power chstrh am maps using incores confirm hot channel RESP 5 2 refers to RESP 61 for performance of factor kmds - total pealung factor & enthalpy rism bot channel

. map then RESP refers to REI 6.1 for computer factor - pnor to 90% and monthly after analysis Acceptance erderia are in RESP 6.1 step 61.1 15 311 B 2 a Axtal flux difference shaR te maintained wdhin allowable RE SP 1.3 gathers data, duects tne analysis, and Control Roorn Stuft togs (PBF-2934 &

defined by Fig. 15310-4 estabashes axial offset constants and duects the 2035) record Ap and refers to 15 310 B 2.a changing of these constants per ICP-10 33. REI for acceptance criteria 12 3 Dena Flux Control step 4 4 references Fig.

15310-4 15 310 B.2 d Alarms shau normally te used to indicate non<onformance RE! 12.3 Delta Flux Control step 4 5 references wah AFD requirements 15 310 B 2 d and provides monnonng method with the PPLS alarms out of serwce 6n step 5 4 15 3.10 B.2 e AFD s.ias be considered to be outside kmits when at least 2 AOP-6B note eucare channels so indicate step 6 15 31 i B.3 Quadrant power int 52%

AOP-6B step 6. REI 13 0 guides operators in response to hit alarm 15.3.10 B 3 d quadrant power talt alarms and afternattve calcutabonal REI 13 0 step 4.1 provides operator actons for alarm methods out of service (including atternate calcs )

15 310 C.1 a An RCCA shan be considered knoperable if the RCCA does Table 15.4.1-289

. AOP4B Att D references these TS sectens not drop upon removal of stationary gnpper cod voltage 15 310 C.1 b An RCCA shat be considered inoperable if the RCCA does Tatie 15.41-2 #10 AOP48 Att D references these TS sections not step property 15.3.10 C.1 c An RCCA Mia8 be considered inoperable af the bank demand Table 15 41-2 #10 AOP48 Att D references these TS sections poston is greater than 215 or 5 30 steps with RPt showing

(

24 steps misahgnment with demand 15 310 C.1 d An RCCA shall be considered inoperable if the demand Table 15 41-2 #10 AOP-60 Att D references these TS sectons

{

posihnn is between 215 and 30 steps and RPI shows l

I l

i l

8

7 TS LCO_.

Description

. TS Surveillance implementing Procedure Comments Cross Reference misahpwrd of 12 steps 15.31 i C 3 fio more than 1 inoperable RCA is permated during Table 15 4.1-2 slo AOP48 Att D references these TS sections sustained prwer operations 15 3 to D.3 a Wdh faded RPt. stuftly postion check of rresakaned or T15 41-1 s19 AOP-6B step 12,27. RESP 1.2, REI 7.0 Rod dropped rod between 10 and 100% ra*ed power Posite Determinaten uses flux mapping to determine rod posaion, RESP 5.1 step 5 3 Cauhon Statement refers to tNs requerement a

15 310 E.1 Rod drop time at operating temperature and flow < 2 2 Table 15.41-2 #9a RESP 3.1 step 6.1.4 references tfiis acceptarre seconds erderson 13 311.A" n-amam of 2 thrrides per quadrant of ancore detectors RESP 1.3 step 5 0 notes that 2 thambles per operable %r recalibraten of encores quadrant need to be operable for cahbration of excores l

15 3.11 B Power kmded to 90% af caldaration requirements for amial RESP 1.3 step 5 0 notes ttus 5ma

,t offset are not rnet 13312.1 Control room emergency fdtration system shail be operable 15411 CL-1D step 2 25 RMSASRB Cl RE-101, during power operation and eefuehng operation of edher urut RMSASRB Cl RE.235 15.3.12 2 a Fitter, adsorber 4 replace test acceptance crderta 15411 HPIP 1154 15 312.2 b Adsorber lab test acceptance enteria 15411 -

HPtP 1154 Lab test results not recorded in procedure I

15.312.2 c Fan test acceptance crsena 15411 HP!P 11.54 153131 Shock suppressors (snubbers) shan be operable during at 15413.1&154.132 CL-1D steps 2 26,3 28,4 36 rnodes except CSD and refuehng 15.3.14 A 1.a Fire suppression weer system, fue main loop water supply, 15 415 A 1 TS-70, TS-71 TS 73. TS-74 OM-3 27 PURPOSE y

both fire pumps sta,it be operable section - enhanced description of fire detection and I

protection systems 15 314 A.2 a Fue suppression water system, water spnnkler systems 15 415 A 2 1S-76, RMP 37 step 2.4 initiates (Ns LCO's Acton ksted in Table 15 314-1 shan be operable Statement 15.3.14 A.3 a Fue suppression water system, fue hose stations in areas 15 415 A.3 TS-75, TS-79 hsted in Table 15 314-1 shan be operable 15.314 A.4 a Halon gaseous suppress 6on systems hsted an Table 15 314-15.4.15 B 1.a TS 78 semiannual hat OtJ 1301 fue suppression 1 shan be operable system serveinance test 15 314 B.1 a Fue detection system purwnts for each area listed in 15 415 B 1 1S-77. TS-78

^

Table 15 314-1 shall be operable 15 314 C.1 a All fire barrier penetration seals protecting safety related 15 415 C.1 OM 3.27 step 1.3 PURPOSE sectiort - describe t

i areas shalt be operable compensatory measures 13.3 in A.1 The overpressure mdgating system shall be operable T15 41-1 #32 CL-10 steps 1.3,2.3,3 4 OP-1 A step 3 2 3 LTOP CL-1D steps 1.3,2.3,3 4 merely state that whenever the RCS is not open to the atmosphere and the mode set per CL-4C.

PORVs operable and Block Valves are temperature is less than the minimum pressurizator temperature for the inservice pressure test open. no mention of I. TOP Mode, no venfication of overprotection system operability 15.315 A.1 a Both PORVs operatAs at a setpoint of 5 425 psig T15.4.1-1 #32, #34 CL-10 steps 1.3,2 3,3 4 4

15 315 A.1 b Both PORVs block valves are open T15 4.1-1 #32, #33 CL-1D steps 1.3,23,34 Tatde 15 41-2 #21b 15 315 B 1 When the RCS is not open and the temperature is 5 275*F T15 41-1 #32 CL-10 steps 1.8,217 & CAunGN statement E

4 9

L..

=

m.

m

.m 2

.u

.m w -..-x w

m

--r.

...-w+,,w~,*-.e.m,

---*ww, y

%-e-w

+vw'"

TS LCO Description

. TS Surveillance implementing Procedure Comments Cross Reference no me,e than 1 tv, pressure Si pump shan tw operata.

15 315 B 2 a A reactor coolant pump sha5 not be started when the T15 41-1 #32 OPAB step 3.18 ternperature is less than the marumum temperature for the nservice pressure ' 2st unless there is a pressure absortang vobrne in the pressunzer or SG tubes 15 315 B 2 b A reactor rMW pump sha3 not be started when the TIS 41 1 #32 CP4B step 3.18 temperature is less than the rrdnamum temperature for the s

Inservice pressure est unless secondary water temperature a less than 50*F above the temperature of the RCS I5 316 A Each reactor coolant system pressure isolation valve Ested in 15416 TS-30 (und 1) & TS-31(Und 2) test these vatves.

Tatde 15 315-1 (S;-845A-F, Sl453A-D. S1467A & B) sha5 CL 10 step 2.27 be functonal as a r' essure isotauen device. Valve leakages sha8 not exceed the amounts anchcated 1

I 10 i

)

e r

TABLE 15.4.1-1 TS LCO

!!em Channel Channel cross Check Calibrate Test Comments Descriptiors 1 Description 2 reference 1,

Nuclear Power Range.

Nuclear Power Range T 15 3.5-282 R: ICP-4 26 (power supphes.

ICP-4 27. rev to, step 2.1.1 -

sununing a level amps,Isolaton erroneous reference to Table amps, txstatde drtvers, recorders, 15 41-1 ttem 1.

channel & A, rneters) 1 Nuclear Power Range Heat 12alance S: OM-4 25-Control Room Shift Da Shift Logs direct ad ustment as Log (PBF-2034 & 2035) heat -

needed per PBF-2034 & 2035 ba!ance results arx! comparison to power range 1

Nuclear Power Range Sigor t.) delta T Q: ICP-2 003, ICP-2 007 1

Nudear Power Range Compare to incore 15310 M. RESP-81 (f!ug snap fol'm ed by check and cailbration of power range), ICP-2 008 axial offset cabbration 2

Huclear tritermediate Nuclear intermediate T 15 3 5-2#3 R. ICP-4 25 (cahbraton), ICP-Range Range 4 38 (compensaton voltage), ICP-4 27 (SR & IR aux $ary channels.

comparator, eate, auda) count iate))

2 Nuclear intermediate Wher net blocked S OM-4.2 5-Cantrot Room Styft Range Log (PBF-2'J34 & l2035) and Control Rocm Cold Ghutdown Log (PFF-2038 & 2039) 2 Nuclear Intermediate logarithmic levet-.

P. ICP-2 009, ICP-2 015 Range bistaue acton 3

Nuclear Source Range Nuclear Source Range T 15.3 5-2#4 R: ICP-4 24 (cahbrahon and btstable NC-103 & 104 adjustments), ICP-2 010 (tustaue NC-101),ICP-4.27 (SR & IR auxiliary channels - comparatar, rate, audo count rate))

3 Nuclear Source Range When not blocked S; OM 4 2.5-Control Room Shift Log (PBF-2034 & 2035) and Control Room Cold Shutdown tog (PBF-2038 8 2039) 3 Nuclear Source Range Bistable action P: ICP-2 010, ICP-2 015 4

Reactor Coolant Reactor Coolant T15.3 5-5 S: OM-4 2.5-Centrol Room Shift R: ICP-41 A (Tu &Tc), ICP-41C Temperature Temperature

18,#19 Log (PBF-2034 & 2035) T and (AT,i), ICP-4.1D (AT a & f(T. ))

m AT recorded and Control Room.

Cold Shutdown Log (PSF-2038 &

2039) cold leg tempesture 4

Reactor Coolard Overtemperature delta T T15 3 5-2#5 Q-ICP42.001 Bistable tests Temperature i tCP-02 001 BL-1, step 7.22.30 OT delta T Rod Stop and Over S

11

=

T TABLE 15,4.1 1 TS LCO ltem Channel.

Channel cross Check

. Calibrate Test' Comments -

'0' Description 1 Description 2 reference Temp Trip, ICP 02403, ICP-

- 02 017, ICP-02.020 4

Reactor Coolart Overpower data T TIS 3 5-286 j

Q-ICP-02.001 Bistable tests, Temperature itCP-02.001 BL-1, step 7 22 32 OP dena T Rod Stop and Over Power Trip, ICP42 017, ICP-02.020 5

Reactor Coolant Flow Reactor Codant Fkm 15 31 G S: OM 4 2.5 Control Room Shirt R: ICP-41K (rack mounted RESP-6 2 & RESP-6.3 Log (PDF-2034 & 2035) and eqwpment), ICP44 002-1 (fbw perform precision RCS flow

- Control Room Cdd Shutdown transmitters) rate measurements (results Log (PBF-2038 & 2039) loop used for PPCS morutoring) fbws recorded 5

Reactor Coolant flow Analog and single loop T15 3 5 2 Q - ICP-02-001, ICP-02 003, loss of flow loge 810a ICP-02 017 -

5 Reactor Coolant Flow Loge for 2 toop loss of T15 3 5-2 R - IC P-02.020 flow s10b 6

Pressurtzer Water its 3 52 89 S; OM42.5-Contrd Room Stuft R: ICP-41J (rack mounted O - ICP42401, ICP-02.033, Level T15 3 5 5 Log (PBF-2034 & 20')5) and equspment), ICP 04 002-3 ICP-02 017, ICP-02 020

20 Contrd Room Cold Shutdown (transmdter cold cat braton Log (PBF-2038 & 2039) pressurizer levelrecorded 7

Pressurtrer Pressure T15 3 5-1 #3 S: OM42 5-Control Room Shift R: ICP-41H (rack mounted Q-ICP 02 001 Bistable tests.

3

~

T15 3 5-2 Log (PBF-2034 & 2035) and equipment), ICP-04 003-itCP-02.001BL-1, step 1.23.1

8,9

. Control Room Cold Shutdown 1(transmater cahbraton) high pressure trip, low pressure T15 3 5-3 Log (PBF-2038 & 2039)

Inp, St. Si unblock and St

1d pressuriter pressure recorded T15 3 5-5 unblock enable, ICP-02 003, ICP-02.005, ICP-02 017. ICP-

16,817 02 019, tCP-02 020 8

Steam Generator L eyet T15 3 51 #7 S: OM42 5-Control Room StWt R ICP-411 (rack mounted Q-ICP-02.001, ICP-02.003, TIS 3 5-2

. Log (PBF-2034 & 2035) and equipmentL ICP-0 4003 2 ICP-02.005, LCP-02 017, ICP-

13 Control Roorn Cold Sheldown (t1ansmitter caiibrabon) 02.019, ICP-02.020 T15 3 5-3 Log (PBF-2038 & 2039)

3at,3b(s)

T15 3 5-4

3a T15.3 5-5

25,#26 9

Steam Generator Flow T15 3 5-2 S; OfA4 2.5-Contrd Room Shift R: ICP-4 I F (steam flow), ICP-O-ICP-02.001, ICP-02 003, Mssmatch

12 Log (PBF-2034 & 2035) 41G (feed flow), ICP44 006-1 ICP-02 017, ICP-02 019, ICP-(steam flow transmaters), ICf'-

02.020 04 007-1 (feed flow transmittel 10 Steam Generator T15 3 5-1 #4 S-OM-4.2 5-Control Room Shift R: ICP-41E (steam pressv e).

O-ICP-02.001, ICP-02.005, Pressure T15 3 5-3 Log (PBF-2034 & 2035) and ICP-04 004-2 (steam prer.sure ICP42.019,ICP 02.020

1c Control Room Cold Shutdown transnutters)

T15 3 5-5 Log (PDF-2038 & 2039) 6 12 m...

TABLE 15.4.1-1 TS LCO ite m Channel Channel Check.

Calibrate Test Comments cross Description 1 Description 2 reference

27 il 4KV Bus Undervoltage AFW Pump actuation T15.3 51 #5 R: 1RMP-9056-3 and 2 RMP-M - RMP-9075 T t 5.3 53 9056-3 Protective relay calibrations

3b0) 11 4KV Bus Undervoltage Reactor Protection T15 3 5-2 R: 1RMP-9056-3 and 2 RMP-M - ICP-02.003, ICP42 010 actuation

14a 9056-3 Protectrve relay calfbrations ICP-02 017 13 4KV Bus to Reactor Coolant T15 3 5-2 R. IRMP-9056-3 and 2 RMP-Underfrequency Pump Trip

14b 9056-3 Protectrve relay canbrations 13 Safeguards Bus Loss of 4KV T153 53 S. OM-4.2 5 Safeguards SNft R: 1RMP-9056-1,2 & 3 and 2 M. RMP-9071 (degraded and RMP-9071, rev 2, step 21 Voaage.

4a(d)

Log (PBF-2136)

RMP-9056-1,2 & 3 Protechve bss of voltage inontNy) -

shouki reference Table relay cahDrations 15 41 1 Item 13 not items 13 Safeguards Bus Degraded 4KV T15 3 5-1 #9 S: OM-4.2 5 Safeguards SNft R: 1RMP-9056-1,2 & 3 and 2 M: RMP-9071 (degraded and RMP-9071, rev 2, step 2.1

36. 37a and 37b Voltage T15 3 5-3 Log (PBF-2136)

RMP-9056-1,2 & 3 Protective loss of voltage rnontNy) should reference Table

4ap) relay caicrabons 15 41-1 Item 13 not items 13 Safeguards Bus Loss of 480V T15 3 5-1 S: OM-4 2.5-Safeguards Shift R 1RMP-90564 & 5 and 2RMP-M, RMP-9071 (degraded ani RMP-9071, rev 2, step 2.1

36. 37a and 37b Voltage

10b Log (PBF-2136) 90564 & 5 Protecbve relay loss of voltage rnanthly) shouk1 reference Table T15.3 5-3 canbrat,ons

4b(i) 15 4.1-1 Item 13 not items 14 ~ ) '20 VAC instrutnent 15 3 7.B 1i W: Turb Bldg Sinft Log (PDF-

36. 37a and 37b lIbes 2032 & 2033), Turb Bldg CSD Log (PBF-207't & 2078). Aux Bldg SNft tog (PBf -2031)-

inverter supptying load 15 Reactor Tnp Signal Turtane Autostop T15 3 5 2 M: ICP 02.003 from Turbine

1ta 15 Reactor Trip Signal Turbine stop Valve T15 3 52 M. ICP-02 003 from Turbine

11b 16 Reactor Tnp Signa!

T15 3 5-2 M. ICP-02.003A-1 step 7.19 from Si

15 17 Feedwater Isolation on MFP Trip on Saiety T15 3 54 R. ORT-3A, ORT-38 S1 SI injection

3b Actuation with Loss of Engineered Safeguards AC 17 Feedwater isolata) on MFRV Shutt ng vi T15 3 5-4 R: ORT-3, ORT-3A, ORT-3B SI tests MFP breaker trip -

51 Safety injechon

3b Actuation with Loss of Engtneered Safeguards AC 18 Accumulator Level and 15 3 3 A S: OM A 2.5. Safeguards Shft >

R: ICP44 004-3 (St accumu!ator tests MFRV & bypass closure Pressure tog (PBF-2136) pressure transmitters). ILP-411 (St accumulator levet transmitters),

I ICP-4.13 (Si accumulator levet &

pressure loops) e 13

. =

~

TABLE 15.4.1-1 TS LCO '

Ite m Channel Chan :I cross Check' Calibrate

. Test

' Comments Descriptiori 1 DescQtiori 2 reference 19 Analog Rod Posdon.

Analog dod Posann 15.3.10 D S: OM-4 2.5. Control Room Shift R. ICP4 29 anakg rod pesom Log (PBF-2034 & 2035) caidaration 19 -

Analog Rod Posibon with st+ ~ countes 15.3 to D S: OM-4 2.5-Control Room SNft Log (PBF-2034 & 2035) 19 Analog Rod Pesalon Monitoring by on-hne 15 3 to D Logged if inep on Control Room computer SNft Log (PBF-2034 & 2035) 20 Atedhary Feeduater T15 3 5 5 8E Cowpath operable prior to power R. ICP-04 006-3 (Und 2 aumdkary Flow '

Ops folkwnng CSD > 30 days; feed flow transmater and sucten IT-290A (Unt 1) & IT,295A (UnR pressure transmiter & Indicator),

2) venfies auxilliary feedwater ICP-04 003-5 (und 1 auxilkary feed flow paths.o each steam flow transmiters). ICP-04 032-1 generator.

(auxilhary feed fk:w and suction pressure electronic cahbratron) 21 Boric Acid Control 1532 R: ICP-414 (boric ackt flow System control system) 32 Boric Acid Tank ievel T15 3 2-1 D: OM-4.2 5-Safeguards SNft R: ICP-415 (BA tank level Log (PBF-2136) transmdters), ICP-4.16 BA (level channels) 23 Charging flow 1532 R: ICP44 003-4 (charging flow transmdter and indicator), ICP-04 032-1 (char (,ing flow electronic cathation) 24 Condensate Storage T15 3 5-5 S: OM-4 2 5, Safeguards Shift R: ICP-13 009-1 (CST tevel Tank Larset

24 Log (PBF+2136) L transmdters cahbration), ICP-13 009-2 (CST levelloop calibratton) 25 Contahynent Hgh T15 3 5-5 #7 S. OM-4 2.5-Control Room Shift R: ICP44 036 (containment high Range Radiation Log (PBF-2034 & 2035) and range rad mondoring system), ICP-Control Room Cold Shutdown 04 036-1 & 2(for unds 1 & 2),

Log (PBF-2038 a 2039)

ICP-13 4 Spec 200 intemals calhation 26 Containrnent Hydrogen Containment Hydrogen T15 3 5-5 D: OM-4 2.5-Control Room SNft Monsor.

Mondor

10

, Control Room Cold Shutdown Log (PBFr2034 & 2035) and -

' Log (PBF-2038 & 2039) 26.

Contatnrnent Hydrogen Gas caihation T15 3 5-5 Q: ICP-13 2 (gas cathation),

Monitor i

10 BCP-13 4 Spec 200 intemals calibration 26 -

Contairawr-e Hydrogen Electronic calibration T15.3 5-5 R: ICP-4 34 (electronic Monitor

10 cahbration) 27 Containment Pressure i15.3 5-1 S: Safeguards Shift Log (PBF-R: ICP-41L (rack mounted Q: ICP-02.001, ICP42.005,

1,2 20Y2) re::ords containment electrorucs). ICP-04 006-2 ICP-02 019, ICP-02.020 T15 3 5-3 pressure, criteria:-1 to +2 psg (containment now, med:um, and

1b,2b wije range pressure transnutters)

T15 3 5-5 I

14 l

s

TABLE 15.4.1 1 TS LCO ltCm Channel Channel cross Check Calibrate Test Comrnents 8

Description 1 Description 2 referetite s21.?2.23 28 Contantnent Water T15 3 5-5 M. OM-4 2.5-Control Room Sh:ft R: ICP-4 22 (level transmitter).

Levei 88.9 Log (PBF-2034 & 2035) and ICP-13 4 Spec 200 interrWs Control Roctn Cold shutdown calabration tog (PBF-2038 & 2039) 29 Emergency Pian Q: EPMP-1.1 Routoe check, R EPMP-1.1 Routtne check.

Q: EPMP 1.1 Routine check, Scheduling of IMrddual Radiation Survey maintenance,cahbraton and maintenance, cahbrabcn and maintenance, calibration and instruments ts not controBed instruments inventory of HP E-Plan anventory of HP E-Plan equipment.

inventory of HP E-Plan by official mear's (not in equipment, Form 1.1b specifies Form 1.1b specifies the number equiprnent. Form 1.1b specifies CHAMPS,no PBF. HP uses the number and types of survey and types of surveyir.strurnents the number and types of survey self generated form to keep instruments (quartertyinventory (quarterly Inventcry and source instruments (quarterly inventory track of survey instruments in and source response tests),

resporse tests). EPMP-1.2 E-Plan and source response tests),

use and their due dates) Don EPMP-1.2 E-Plan equtpment equtpment routine check.

EPMP-1.2 E-Ptan equipment Lectait sant HP is removing routine check, maintenance, and maintenance, and cahtuation routine check maintenance. and all bstruments from cahbraton instrucitans invches instructions awokes HPCAL-l.1 cahbraton instructions invokes CHAMPS and have HPCAL-1.3 for response checks for calibrations of portable sunrey HPCAL-1.3 for response procedure changes mstruments (step 61 1.d states checks generated. E-Plan rad schedule is estabhshed usn}

CHAMPS) morutor cats and response tests areAW be fully controlled by EPMP-1.1 Form t.lb HPCAL-1 1 should reference Table 15 41-1 trem 29 tot Item 27 EPMP-1.1 and t.2 steund reference Table 15 41-1 30 Environmental M. Monthly checks are no. longer Monthly Environmental Monitors

^

Item 29 NOT 30 conducted-Quarterly checks are 2

done under TS 15 7.7 via PDNP Mondor checks are no longer Environmental Manual conducted Testingis performed quarterty per TatAe 15 7 7-1. CR needs to be written to resolve Table 15 41-1 error (Environmental morutors should not appear 31 in-Core T15 3 5 5 M: RESP-6.1 (TC map printed at R: RESP-31 (TC map printed 6n Table 15 41 1)

Thermocouples st3 power, ternperatures reviewed during heatup, temperatures against acceptance crReria.

compared to Tw check 3 2 TCs check t 2 TCs per quadrant per quadrant operable) operable)

Note :cabbraban is to observe response to source 32 Overpressure 15315 S-OM-4 2 5-Control Room Shift R: ICP-04 004 6 (transnutter Channel functional when 15 s

TABLE 15,4.1 1 TS LCO ttem Channet Channel cross

Check, Calibrate Test Comments -

Description 1 Description 2 reference Akt@ating System Log (PBF-2034 & 2035) and castxations) requred to be operatne; ICP-Contrd Room Cold Shutdown 2.16 Overpressure Mitigeting '

Loa (PBF-2038 & 2039)

System 33 PORV Black Vane 15 31 A 5 a Q: IT-20(ftidualcheckof Una R: IT-200 (una 1 check nsing IT-200/205 are checks not Poseon indcator T15 3 5-5 #2

' 1 posshoq Indcation),IT stem Indicat,.r wsth control board cabbrations.

(functionil check of Un!t 2 open/ closed posaton), IT-205 (Una position indication),IT-200 & 205 2 dato)

(performed during CSO-sat:sfies

check" requirement) 34 PORV Operabitay 15 31 A 5 a R. ICP-4 IH (analog racks -

Q: ICP-02.001, ICP-02.020 pressurtzer pressure), ICP-4 004-6(LTOP transmitter cahbrations) 35 PORV Posamn T15 3 5 5 #1 S: OPA4 2.5-Cvonvi Room Shift R: 1T-200 (Una 1 local % vake R: IT-200 (Una 1 local % valve iT-200/205 are checks nct Indicator Log (PBF-2034 & 2035) and posaion indicaten compared to positen indicatson cornpared to cahbratens control Room Cold Shutdown control board openiciosed control board open/ closed Log (PBF-2038 & 2039) indicaten & *tJat Shut' indication & *Not Shut

annunciator), IT-205 (Unit 2 krat

. annunciator),IT-205 (Una 2

% vane posaion indcat:on local % vane position Indication compared to control board compared to control board open/ closed indication & *tJot open/ closed indication & *Not..

Shut" annunciator)

Shut" annt4ior) 38 Rad!ation Monitonng T15 3 55 D. OM-4 2 5-Control Room Shirt R: ICP-13 001-1, 2, 3, 5 (R F.-218 M: TS-9 RE-101 & RE-235 HPIP-7.51 Tech Spec System

13 Log (PDF-2034 & 2035) and waste disposal system hquid.

functional check (control room references are too renerat.

(RETS & TS checks) -

Contrc4 Room Cold Shutdown RE220 SFP hquki, RE223 waste vent alarms, dampers shift, fan Compared PBF 4006f thru s (non-RETS cats)

Log (PBF-2038 & 2039) distdtate release liquad, RE230 start),HPIP-7,51 Monthly to SAR Tables 11.24A,7A hquu.I retention pond discharge, operahonal test of the rad!ation

& 8. RE-237B (background RE-234 control room vent loane, monitoring system (daughter for TSC iodine montor) and RE-234B RE234 background. RE-procedures reference PBF-1(2)RE-302 (Rod d.se room 235 control room vent nob le gas, 4006f s) a monnor) not on forms.

C261 Aux BLig exhaust, C262 SAR change (FCR 97-010) drumming area vent, RE-214 PAB in for ehmanation of 1(2)RE-exhaust ventdation gas, RE-221 302. CR needs to be wtaten drumrning area vent gas, RE-224 to disconnect RE-2378, gas stripper bidg exhaust, & RE-abandon in-place, and 225 combined air ejector low remove from SAR range), IICP-13 001-1 (1RE-216 cont. fan cooler hqutd,1RE-219 S/G blowdown hquid,1RE-229 service water outlet), IICP-13 001-2 (I RE-211 cont. air particulate.

1RE-211B RE-211 background, 1RE-212 cont. noble gas), llCP-13 001-3 (C259 cont purge exhaust),11CP-13 001-5 (1R E215 condenser air elector gas,1 R E-16

TABLE 15.4.1-1 TS LCO llem Channel Channel cross Check Calibrate Test comments O

Descriptior: 1_

Descriptior12 reference 217 CCW water hquid) 37 Reactor Vessel FAdd T15 3 5-5 M. Control Room Shift Log (PBF-R: ilCP-04 0034 (LT-44' &

Level System

11,12 2034 & 2035) and Control Room 477A cahtwaten), tCP C4 023-1 Cold Shutdown Log (PBF-2038 &

(reactor vesselwide and narrow 2039) range level transmater cahbraton)

ICP-13 4 Spec 200 irdernals cabbratnn 33 Refueting Water T15 3 5-5 R: ICP-4.19 Storage Tank levet

15 39 Residual Heat R. ICP-419 Removat Pump Flow CD Safety Vatve Position T15 3 5-5 #3 M: TS-32 Safety vatve position R: RMP-9054-1 & 2 each check RMPs have no Tech Spec tridicator :

verification, subcooling margirl -

PZR safety valve position references monitor check, containment purge indicators, RMP-9054 3 performs vahe position check cahtwaton 41 Subcoobng Marge T15 3 5-5 #4 M TS42 Safety vata position R: ICP-13 4 Spec 200 internals Monitcr venfication, subcooftng margin cahtwation monitor chec6, containment purge valve position check 42 Tt. tam Overspeed independent Overspeed 15 3 4 F R: ICP-04 028-1 (overspeed M: ICP-02 012 Trips Protectm System cal:bratwan and inp and alarm setpoents) 42 Turbine Ourspeed

.heryetd Bluck trip 15 3 4 F R: ORT-4 (functionaltest)

M. OM4 25 Main Turbine stop tJo cahtxation procedure Tnpa overspeeds tu tme and records and Governor Varves with found rpm where mecharucalinp Turbine Trip Test (TS-3 & 4) actuates - operators directed to tests the turbine trip block contact Marntenanceif tripis overspeed inp. Turbine Trip outside allowable rpm range.

Test (TS-3A & 4A) tests the turtxne trip block overspeed trip 43 Volume Control Tank R: ICP-418 (VCT level), ICP-teye; 04 003-3 (VCT level transmrtter )

44 Reactor Protection M: ICP42.003,1CP42 005 p

System and Emergency Safety Feature Actuation System Logic 45 ReactorTrip System.

Intermeduste Range 15232 Rs R: ICP-02.000-1 (pre-startup.

Interlocks tJeutron flux, P 6 includes bistable sp adiustment) 45 Reactor Trip System Powei Range tJeutron 15232 Rs.

R; ICP-02 015-1,1CP42.014-1 Interiocks Flux, P-8 (pre-startup, includes bistable j

sp adiustment) 45 Reactor Trip System Power Range fJeutron 15232 R:-,

R: ICP-02 015-1, ICP-02 014-1 Interlocks Flux, P-9 (pre startup, includes b! stable sp adjustment) 17 J

s TABLE 15.4.1-1 TS LCO ltem Channel Char el cross Check Calibrate Test comments Description 1 Desc. pliori 2 reference 45 Reactor Trip Systern Pcmer.tange Neutron 15232 R.- +

R: ICP-02 014-1 (pre-startup, Interlocks Flu

P-10 includes bistable sp adjustment) 45 Reactor Tno System 1" Sta a Turbane R. ICP-41J (rack mounted R: ICP-02.015-1,10P42 020-

! erlocks Int imputa Pressure. P-7 equipment to rod control a steam 1(pre startup, includes bistatge dump) ICP44 010-1 sp ad ustment) l Test TABLE 15.4.1-2 TS LCO ITEM Description cross Frequency Test Procedure

. Comments 8

reference 1

Reactor Cootant Samp4es Gross Beta gamma activity 15 31 C SAveek CAMP-101

_{encludnj Tritium) 1 Reactor Coolant Samples Trdaum actrvdy 15 31 C monthl/

CAMP 101 1

Reactor Cootant samples Radiochemical E deterrnination 15 31 C serruannually CAMP-406 (E bar detenn6 nation) 1 Reactor Coolant Samples Isotopic anafysis for dose 15 31 C every 2 weeks CAMP-101 equivalent 5-131 Concentration 1

Reactor Coolant Samples isotope analysis for lodine 15 31 C OP-3A step 214 CAMP-101 includ:ng 1-131,1-133, and 1-135 reactor coolant sample following 15% power change 1

Reactor Coolant Samples Chkuide concentration 15 31 E CAMP-101 1

Reactor Coolant Samples Dess Orygen concentration 15 31 E CAMP-101 1

Reactor Cociant Samples Fluoride concentration 15 31 E CAMP-101 2

Reactor Coolant Boron Baron concentration 15385 CAMP-101, 3

Refueling Water Storage Baron concentiation 15 3 3 A.1.a CAMP-101 Tank Water Sample -

4 Boric Acid Tanks Boron concentration T15 3 2-1 CAMP-101 5

Spraw Addove Tank flaOH concentsation 15 3 3 B.1 a CAMP-1001 Sample fiequency not spec 4fied in CAMP-10t 6

Accumulator Bcron concentration 15 3 3 A.1 b CAMP-1001 Sample frequency not specified in CAMP-101 7a Spent Fuel Pat Boron concentration CAMP 101 7b Spent Fuel Pd Water level venfication OM4 2 5-Aux Bkig Stuft Log (PBF-2031), local indicator,63 to 64 feet 8

Secondary Coolard Gross Beta gamma activity or CAMP-101 gamma isotopic analysis 8

Secondary Coolant lodtne concentration 15 3 4 B CAMP-101 9a Control Rods Rod drop isrnes of all fun length 15 3 to E RESP-3.1 cold and hot rod drop tests rods 9b Contrd Rods Rodworth rneasurements 15310 RESP-4 2 rod wonh measurement following RESP-4 2 does not reference TS Tabla crdica3 15 41-2 dem Ob 18 l

. TABLE 15.4.1-2.

TS LCO ITEM Descriptfori Test cross Frequency Test Procedure Comments reference 10 Contal Rod Partial movemere of as rods 15 3.10 C OM-4 2ABkWeekly Rod Exercise Test Ura 1 7 2 (TS-5 & 6) exercaes control and shutixm rods 11 Pressuruer Safety vanes set pomt 15 31 A 4 RMP-9054-1 PZR safety watwo removat and valve setting done by outside vendor-Instanation (rerrmes, packages for sh!ppersg. &.

vendor work travelers should contaan as-reinstalls vanes) found & as left settings 12 Main Stevn Safety Va!ves Set pr.nnt 15 3 4 A 1 RMP-55 Main steam safety vaNo rernovat vatve setting done by outsks s vendor-(removes, packages for shipping; & rekista5s vendor wo:k travelers shouu contain as-

~

valves) found & as-left settmas 13 Cordaloment isotatxx) Trip Functioning OM-4.2.5-ORT-3, ORT 3A, ORT-38 SI Actuation wth Loss of Engineered Safeguards AC tests containtnent isolation response, HPIP-7.516 containment purge & vent on high rad 14 Refuehng System Functioning CM-4 2 5-ORT-15 Fuet Manipulator and Fuel Intertoch s Transfer System interiock tests 15 Sennce Water System Functioning 15 3 3 D OM-4.25 ORT-3, ORT 3A ORT 3B Si -

Actuation with Loss of Engineered Safeguards AC tests service water system response 16 Pnmary System Leakage Evatuate 15310 OMA 2SControl Roorn Shift Log Urut 1 & 2 PBF-2034 & 2035 do net speury leakage

}

(PBF-2034 & 2035) calculate and record '

timd leakage 1V Dese! Fuel Suppty f uel inventory 15 3 7 A 1 e OM42.5-Safeguards Shift Log (PBF-2036) l Diesel Day Tank levels A Tank (LI-3932) 60 -

89% B Tank (Li-3934) 60 - 89%, Turb Bldg Log (PBF-2032) Diesel Generators G01 & G02 Sump Tank fuellevels > 400 gal. Turb Bldg Log (2033) Diesel Generators G03 & G04 Day Tank levets (LIT-3992A/B) 815 100%

Storagq Tank Levels (LIT-3985A/B) 64 95%,

Turb B1dg CSD Log (PBF-2077/2078) same as PBF-2032/2033 18 Turbine Stop and Governor FunctKaung 15 3 4 G OM-4 2.5 Matri Turbine Stop and Governor Vatves Valves with Turbine Trip Test unit 1 & 2 (TS-3

& 4) tests valve closure. OP-1C tests valves on turbine startup 19 Low Pressure Turbine Visual and magnetc parucle er Syrs RMP-63 LP turbine rotor inspection Rotor inspection hquid penetrant 20 Bonc Acid System Storage Tank and piping T15 5 2-1 dady OM-4 25Auxdiary Bldg. Shift Log (PBF-2031)-

OM-4 2.5 Survemance requirement of temperature a temperature as Bonc Acid Tanks Temperature (1/2TI 107&TI-temperatures t 145*F is incorrect. Also, required by Table 15 3 2-1 103),80 - 120*F (no check for concentration),

TS reference shoukt be Table 15 4.1-2 (concentratton, temperature)

Bono Acid Piping check (TR-4177) recorder (ttem 20) root Item 21. Further, operating and no sensor points in alarm or Survemance Requirement far

Test boric bypass (references Ol 99A) acid piping heat tracing circun operabdsty" should be deleted PDF 2031 should read e

19

TABLE 15.4.1 2 TS LCO -

ITEM Description -

Test cross Frequency '

Test Procedure Comments 8

' reference "Bcric Ack1 Piping Temperaturel rot Boric Acid ' Heat Tracing Recorder.*

Bla PORV Block Vanes Complete vane cycle 15 31 A 5 0: OM-4 2,5-IT-20 (stroke timing Unst 1), IT-25 (stroke timing Unit 2), IT-200 & 205 (ddto during CsD) 21b PORV Block Vanes Open position check 15315 72 hrs wtien overpressure mdgation system,

Logs do not specify acceptwie position 15 31 A 5 required to be operable: Control Room Stift Log as being open wt.en overpressure i

Unit 1 & 2 (PBF 2034 & 2035) and Control.

megation system required to be operable k

Room Cold Shutdown Log Unst 1 & 2 (PBF.

22 Irdegrey of Post Accident Evaluate 2038 & 2039) check valve postion each refuehog cycle IT-500 SERIES (except 560 for test cf CVCS IT-510B step 1.2 incorrect refe ence to Recovery Systems outside holdup tanks and 570 fx drain systam)

TS Table 15 41-2(24). IT-5158 step 12 Containment procedures for systerrvcomponent leak testing.

incorrect reference to TS Table 15 41-monitonng, and preventive maintenance.

2(24) IT-5458 (Containment spray) does not reference TS Table 15 41-2(22),

there is no CS procedure for Urut 1-Procedure is being developed ( IT-545A77) 23 Containment Purge Supply Venf salves are locked closed 15 3 6 A 1 c OM42 5-Containment Purge Valve Posmon OM-4 2 5 TS reference stould be Table _

f and Exhaust isolation (TS-32) vakes position indication closed and 15 41-2 (! tem 23) not item 25 Vanes switches locked 24a Reactor Trtp Breakera Venfy independent operabihty of T15 3 5-2 ICP-2.018-1,ICP-2 003ASB 1,ICP-2 017-1, automatic shunt and

17 (CP-2 023A&B-1, lCP-2 021ASB-1, lCP-2 015-undervoltage trip functions 1

24b Reactor Trip Breakers Verify independent operabildy of TIS 3 5-2 ICP-2.018-1

~

manual tnp to shunt and

17 undervoltage tnp functions 25a Reactor Trip Bypass Venfy operabtitty of the ICP-2.003, ICP-2 003A&B-1, ICP-2 017-1, Breakers undervonage inp function ICP-2 023A&B-1, ICP-2.024A&B-1, ICP-2 015-1 25b Reactor Trh Bypass Venty operabihty of the shunt ICP-2.003. lCP-2 003A&B-1, ICP-2.017-1, Breakers inp functions ICP-2 023A&B 1, ICP-2.024AS B-1, ICP-2 015-1 25c Reactor Trip Dypass venty operabihty of the manual IC P-2.18 Breakers inp to undervoltage inp functions 26 120 VAC VitalInstrument Venty energized 15 3 7 A 1 h Turb Bldg Shift Log (PBF-2032). Turb Bldg OM-4 2 5, erroneous references to CR Bus Power CSD 1.og (PBF-2077) chec' eiter output Shift Log (PBF-2034f2035,2040/2041),

voltage and amps and invei, epplying load CR CSD Log (PBF-2038/2039) tamp indication for Inverters ),

'01,1 DYO2, DYOA, DYOB,2DY01,2DYO2, Aux Bldg Shift Log (PBF-2031)-Static Transfer Switct:

Position (i e, irwerter supplying load) and Voitage (114 to 130 volts) for buses 1DYO3, DYOC,20YO3.1DYO4. DYOD and 20YO4 20 s

TABLE 15.4.1 2 TS LCO ITEM Descriptio 2" in dia the new welds will recerve both a mod:ficahon t4DE requaements surface end 100% volumetnc NDE for power piping 15 4 3 c When prunary system rnods or repairs have been made v.hsch 6nvolve new 1531O NP-7.4 3 Post maintenance and strength welds on components 12" in dia the new weids wr!! receive a sus face modihcahon NDE requirements NDE for power piping 1544i Perfarm required visual examinations and leakage rate testing in accordance 15 3 6 E CL-10 step 2 36. TS-10 Local CL-1D step 2 36 Tech Spec reference should with the Containtnent t eakage Rate Testing Program leak teshng of containment be 15,4.4.1 personnel hatches. TS-10A Containment aniock door seat ED 15 4411 Tendon Survealance 1536 CL-10 step 2 41 CL-10 step 2 36 Tecta Spec reference should be 15.4.4,ti, til, IV 15 4 4 til End anchorage concrete survedlance 1536 Cl-1D step 2 41 CL.10 step 2 36 Tech Spec reference should 21

+

TS Section Surveillance Requirement TS LCO Implementing Comments 4

cross Procedure reference be 15,4,4.11, Ill. IV t5 4 4 IV Liner Plate 15.3 6 CL-1D step 2.41 CL-10 step 2 36 Tech Spec seference should be 15.4.4.11. Ill. ;V 15 4 j a A 1.a The safety injection system tests shat be performed with RCS pressure 5350 15 3 3 A ORT-3 or ORT-3A & 38 psig and temperature 5 350*F. A test SI signal will inaiate operation of the Table 15 3 5-3 83a r

system, motor tweakers for the S1 & RHR pumps may be racked to test or racked 6n 15.0.5 I A 2 The safety injection system tests will be considered sabsfactory if control 15 3 3 A ORT-3 or ORT 3A & 38,ICP-board indicatior, and visual observations indicate that alh.u,,W-As have 10 22 (11C support - vertfcation received the si signalin the proper sequence and timang of selected relay proper actuation) 15 4 5 i B.1 Containment spray system tests performed with spray to contanment blocked, 15338 ORT-6 irutsated from normal actuation instrumentaten, breaken s for pumps in the test posmon i

15 4 5 i B 2 Test satisfactory if vrsual observations indicate all cornponents have operated 15 3 3 B ORT-6 sahsfactordy 15 4 5 i B 3 Spray r,ozJtes that be Ctwcked to venfy that they are not obstructed every 5 15 3 3 B TS-37 (Una 1) & TS-38 (Urut 2) yrs Containmert spray nozzle check 15 4 5 i C.1 Contairment fan coolers shaB be tested at each refuehng outage to venfy 15 3 3 B ORT-3 (servre water bypass proper operahon of the backdraft dampers and the service water bypass valves vatves), ORT-7(operation of the backdraft dampers) 15 4 E I C 2 Containment fan cooler accident fans tested monthly, fans start and rou eg 153 3 B TS-33 (una 1) & TS-34 (una 2)

Procedurws do not test fan start unless not currert venfied.

containment accident a'. ready running recirculation fan cooler rnonthly test (starts any fan not running and measures amps)

' 15 4 5 II A 1 SI, RitR, and containment spray pumps shaR be tested in accordance with the 15 3 3 A IT-01, IT-02, IT-03, IT-03A, IT-

[

IST Program 15338 04, IT-04A, IT-05, 4T-06 15 4 5 II A_2 Acceptable levels of performance shall ' e that the pumps start, reach their 15 3 3 A IT-01, IT-02, IT-03, IT-03A, IT-This conclusory statement is not explicaly 1

required developed head and operate for at least 15 minutes on the full flow 15 3 3 B 04, IT-04A, IT-05, IT-06 dwect reiterated in any pump test procedure test lines the operation of purnps for a ANALYSIS section minimum of 15 minutes before s

performance data is taken. IT-The e is no longer a standing order book -

01,02,3A,4A reference the 6

Operations Statu. ng Order as 1

containing pomp and vatve operabahty ctdena wtute IT-03,04, 05,06 reference the IST Acceptance Criteria Binder.

15 4 5 il B 1 At least every refuehng, venfy by visualinspection each containment sump PC-24 step 6 5 3 l

suction inlet is not restncted by debris, detwls strainers are ok structurally 15 4 511 B 2 Venfy each manual, power operated and automatic valve necessary to insure '

15 3 3 A Per Operations all of ttusse valves system operabihty in ECCS and CS, not secured in posihon, is in conect 15338 are secured in position, therefore

+

posden once every 31 days no survedlance ts performed e

1 22

~.

d

TJ Section Surveillance Requirement TS LCO Implementing Comments cross Procedure reference 15 4 6 A.1 Desel generator rnonthly manual test (start, load and run) 15 3.7 B.1 f.g.h TS-81 (G41), TS-82 (G-02) TS-83(G43) TS-84(G44)

Emergency diesel monthly 15 4 6 Al Diesel generatcrauto start (on actualloss of AC wt simulated SI), load shed, 15 3 7 B.1 f g.h OR T-3, OR T-3A, OR T-38 load sequence 15.4 6 A 3 Proper operation of emergency aghting inckxhng automatic switch to DC ORT-3, OR T-3A, GR T-3B DC Eghtmg verifed only in control room.

demonstrated dunng each refuehng Attachment A Bases speak of Eghting in certain safeguart,4 equipment areas and that the test verifles that

[

the automatic transfer swach operates property and provides power to the DC emergency nghting 15 4 6 A 4 Diesel generator inspection per vendor rew mendations 15.3 7 81.f.g.h RMP-9043-1 EDG G41 Train A Preventive maintenance invokes the folkung RMP-9043-11 (2 year elecincat inspectm), RMP-9043-12 (protective relay cahbratm), RMP-9043-13 (2 year rnechanical inspection),

RMP-9043-14 (6 & 12 year mechanical mspection), RMP-9043-16 (mine power pack inspection). ICP-13 007A-1 (24 mo instrument cakbration), RMP-9325 (416 KV breaker maintenance) RMP-9043-4 EDG G41 Train B Preventrve mantenance envokes the fol'.cwing RMP-904341 (2 year electricalInspectton), RMP-9043-y 42 (protective relay calibration),

RMP-9043-43 (2 year nachanical inspection), RMP-9043-14 (6 & 12 year mechanicai inspection), RMP-9043-16 (meni power pack inspection), ICP-13 0078-2 (24 mo instrument cahbration), RMP-9353 (4.16 KV breaker maintenance) 15 4 6 A 5 Monthly diesel fuel ott system operabildy verified 15.3 7.B.1.f.g.h TS-81 (G41). TS-82 (G 42). TS -

83 (G43), TS-84 (G 04)

Emergency dieset monttdy Attachmerds B (Fuel oil sump tank pump operabdity) 13 4 6 A 6 Diesel fuel oit testmg program 15 3 7.01.f.g.h TS-80 obtains samples, sends to lab and compares results to 23

z T3 Section..
Sufveillano Requirement TS LCO implementing Comments
.y cross _
Procedure reference -
acceptance craetta for fuel oil storage tanks T-175A & B and EDG day tanks T-31 A & B & T-176A & B (quartetty) 154631 Safety related battenes monthly cell voltage, pilot ceR spectfc gravdy and 15 3 7 A 1 f RMP-9046-1 temperature 154682 Safety related batteries every 3 mos==!fe gravdy, height of electrolyte, 15 3 7 A.1.f RMP-9046-1 amount of water added to each ce8 and temperature of every fifth ceB 15 4 6 B 3 Each time data is recorded new data shau be (.umpared to old 15 3 7 A 1 f RMP-90-16-1 15 4 6 B 4 a Each safety related batsery shaR be denumirated operable at least once per 15 3 7 A.1 i RMP-9200, RMP-9200-1, RMP-18 mos by a service test 9200-2, RMP-9200-3, RMP-9200-4 RMP-E200 5 15 4 6 8 4 b Each safety related battery shat be demonstrated operable at least once per 15 3 7 A.1 f RMP-9200, RMP-9200-1, RMP-60 mos by a battery escharge test 9200-2, RMP-9200-3, RMP-i 9200-4, RMP-9200-5 15 4 6 B 4 c Annual escharge tests if battery shows signs of degradation or rjached 85%
15 3 7 A.1 f RMP-9200 cf expected 6fa t
15 4 7 A Main steam stop valves fonowing refuel with closure times < 5 sec from signal 1534O TS-39 (UnA 1) & TS-40 (und 2) should test be from an automate close signal-Indsaten to valve closed test MSIV closure < 5 sec (close bases refer to instrument response time for signal from control room swdch),
steam break??
IT-280,280A,2808,285,285A, 2858 for unas 15 2 also test '
MSIV closure < 5 sec (close signal from control room switch on test buttons) 15.478 tion-return check valves tested for operabody during refuehng 15 3 4 D IT-310 (und 1) & IT-315 (und 2) performs operatAty testing during refuehng (closure torque measurement w/ torque wrench) 15 4 8.1 a Each mata driven AFW pump wdl be started quarterly 15 3 4 A IT-10 Test of electrically dnven 15 3 4 C AFW pumps and valves 15 4 8 4.h Each steara drtsen AFW pump will be started quarterly 15 3 4 A IT.08A (und 1) & IT-09A (Und 2) 15 3 4 C cold fast start of the turtane drtven AFW pump 15 4 81 c The AFW pump discharge and service water supply valves on the suction side 15.3 4 A IT-08, IT-08A, IT-03, IT-09A, IT-win be tested quarterly by operator action 15 3 4 C 10, IT-10A stroke time these valves 15.482 AFW tests considered satisfactory if control board indication and sutsequent 15 3 4 A This corclusory statement is not exphcaly visual observation of equipment demonstrate all components have operated 1C34C property reiterated in any AFW test procedure ANAL.YSIS section 1549 Reactivty anomahes-the actual boron concentration shall be compared to RESP 4 5 performs a teactivity i
predscted periodicaly anomaly check on a monthly basis 154111 Control room emergency futraton once per year pressure drop < 6" H O at 15312 NP-4 3 2 HPtP-1154 step 5 4 2
4 -
24 I
=
= - -..
y l
TS Section Surveillance Requirement TS LCO Implementing Comments i
cross Procedure -
l reference design flow 13 41 L2 Control room emergency futraten once per year auto trutiaton 15 3.12 TS-9 (rrathry) RE-101 & RE-TS 15 411.2 & 3 not referenced 235 used to truttate start (alarms, I
e dampers shift, fart start & n.in),
[
ORT-3 15411.3 Control room emergency fdtration operated at least t o hrs every month 15312 TS-9 (monthtg each of 2 fans t
run for 5 hrs 15 4114 a HEPA and adsorber test and anatysis once per year or after 720 hrs of 15312 t4P-4 3 2. HP1P-1154 trvplace test results are not documented and operation since last test, after painting, fire or chemical release compared with acceptance creena in HPtP-11.54 There are no knks between 720 hrs, and after -
i painting, twe or ct.amical release and performance of tests 15 411.4 b Cold DOP test following fdter changeout or structural work 15312 NP-4 3 2. HPtP-1154 lhere are no links between changeout or structural work and test and performance of tests 15 411.4 c Halogenated hydrocarbon testog following adsorber replacements or structural 15312 NP-4 3 2. HPIP-1154 There are no inks between changeout or woik structurat work and test
?
15 411.4 d Lab analysis of irvplace adsorber once per year or every 720 hrs of service 15312 NP-4 3 2. HPIP-1154 Lab test results are not documented and compared wth acceptance creeria in HP!P-M 54 I
15 4 I L4 e Fans tested once per year or every 720 hrs of operation and following fan 15312 NP-4 3 2, ttPtP-1154 There are no knks between 720 hrs, and after maintanart,
fan maintenance 15 412 B.1 Each sealed source. shall be tested for leakage and/or conta.ntnation at HP-4 3 2, PBF-4017a t
intervals not exceeding 6 mos 15 412 B 2 -
Stored sources shalt be tested for leakage prior to use or transfer HPIP-8 5 Sealed source leak testing step 916 d 15412.83 Startup sources shall be leW tested prior to and following maintenance and IIPIP-8 5 Sealed source leak before being sutgett to core fluu testing step 915 154131 Shock suppressors (snubbers) shat be visually inspected to verify operability 15313 CL-ID step 3 32, RMP-9060 i
en accordance with the following schedule..
safety related snubber visual I
inspection for operabihty, I
determines next inspect.on interval, and updates cauuPs 15 41l,2 During each refuehng 10% of the snubbers shan be functionally tested for 15313 CMP-101 step 41.1 specifies operability.
selection of snubbers to be tested, RMP 61 performs sr'N functional testing 154141 Au shngs and special hfting devices used in supporting heavy loads from either RP-7 step 4 6 the main or auxilhary hoist of the auxiliary building crane shall be inspected Immediately prior to use l
5 15 415 A.1 a Fue suppression system fire main loop water supply valve posdion verification -
15314 TS-73 monthly fire protection TSs related to rire suppression and detection monthly control valve posdion systems do not have explicit references to the
[
TS requirements they satisfy 25 l
2
e.
Y-R 1
TS Section "
Surveillance Requirement TS LCO Implementing Comments
+
cross '
Procedure reference 15 415.A.1 b fue suppressica system fue man loop water supply fre pump functional-15314 TS-70 monthy diesel engine monthy driven fue pump functonaland venfies, TS-71 monthy electnc motor driven fire pump functional 15 4 45 A.1 c Fra suppression system fue main loop water supply fue pump capae*y -
15.3 14 TS-72 annual fue pump capacity yearty test 15 415 A.1.d 1 Fee suppressten system flre man loop water supply diesel pump engme fuet 15314 TS-70 refdts day tank of needed vokrne - morthly after sun test 15.4 WA.1.d 2 Fre suppressAn system fue mam loop water supply diesel pump engine fuel 15 3.14 TS-80 quarterly samphng of fuel Diesel fue pump day tank (T-30)is not analysis - quartetty oil tanks (inct T-72 supplies sampled.
diesel fre pump) 15 4 e5 A.1 d 3 Fue suppression system fue man loop water supply diesel pump engirs 15 3.14 RMP-37 Diesel fire pump engine periodic inspec. hon - 18 mo penodicinspection -
8 15.415 A 3 e 1 Fre suppression system fue main kiop water supply diesel pump battery and 15314 Turtune txand ng stuft tog Unit 2 charger battery voltage vesification - weekly (PBF-2033) 15 415 A.1 e 2 Fue suppression system fire main loop water supply diesel pump battery and 15314 Turbine budding shift log Ordt 2 charger electrolyte level-weekty (PBF-2033) 15 415 A.1 e_3 Fue suppression system fue main loop water supply diesel pump battery and 15314 RMP-9094 charger electrohte spectric gravey - quarterly 15 415 A_1 e 4 Fue suppression system fue main loop water supply dieset pump battery and 15.3 14 RMP-9094 charger periodic inspection - 18 mo 15 4 :5 A 2 a Fue suppression system water sprinider systems vatve position verification -
15314 TS-73 rnonthly fre protection montnty control vatve position 15 4.15 A.2 b Fue suppressim system water spnnkler systems inspector's test - yearly 15314 TS-74 annual underground fire main flow test. TS-76 quartery automatic sprinkter and water spray system sunneillance test f
15 415 A 2 c Fue suppression system water sprinkler systems visual header and nozzle 15314 TS-76 quarterly automatic inspection - 18 mo sprinkler and water spray system I
4 survedlance test step 4 6.1 visual l
15.415 A 3 a Fire suppression system firu hose stations visual inspection - monthly 15314 TS-79 monthly surventance of fue
{
Inspection t
hose stations 15 415 A.3 b Fra suppressnn system fue hose stations hydro - 2 yrs 15314 TS-75 biennial service testeg of fue base and fue hose stations 15 415 A 3 c Fire suppression system fue hose stations valve cycle test - 3 yrs 15fi 14 TS-75 biennial service testing of fre hose and fue hose stations 15 4.15 A 4 a Fue suppression system Halon gaseous suppression systems Halon 15314 TS-78 checks agent quality in venfication - 6 mos March & September 15 415 A 4 b Fire suppression system Halon gaseous suppression systems funcikaial test -
15.3 14 TS-78 performs functional test in yearly march i
15 415 A 4 c Fire suppressmo system Halon gaseous =4pession systems visual header
'5314 TS-78 checks discharge nozzles l
and nozzle inspection - yearty and remaining components in Maech e
26 I
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _,.. _ - - _ _ _. _. - - _. -- _..- -~._,~,. - -
e L
TS Section Surveillance Requirement TS LCO I mplementing Comments i
cross Procedure N
reference 15.415 8.1.a Fue detecten system channel functmal test - 6 mo 15314 TS-77 sems annual smoke TS-77 & 78 do not reference tne Tech Spec detection system mtegrty test, surventance criena, TS-78 sectens 4 3 TS-78 semih HALON 1301 (system operaten and alarm funchonal test) rwe suppression system and 4 4 (heat detector test and hose surver."ance test sections 41 hydrostatic test) are performed annually -
(smoke detecton orsy)
Investigata further. Tatde 15.3.1+1 lists smoke detectors only - smoke tested semi annually per TS. heat tested annuaRy per good practices (Codes. Standards?)
15 415 C 1 a Fre barrw poetratm seals vmual trtspecta - 18 mo 15314 RMP-57,58. 59 15 416 A Penode leakage testing on each valve in TatAe 15 416-1 (St-845A-F, St-15316 TS-30 (Urut 1) & TS 31(Und 2) 853A-D. SI-867A & B) every refuehng, every CSD if for 72 hrs if not tested in test these vatves last 9 ma and after mantenance or repair a
I b
27
i CONDITION REPORT CR 97-0723 j
STATUS: OPEN UNIT: 1 SYSTEM: TU INITIATED: 03/04/97 CT.OAED :
MSS #:
ADMINISTRATOR:
INITIRTOR:
ISSUE MANAGER:
NUMBER OF OPEN ACTIONS:
1 NUMBER OF CLOSED ACTIONS:
0 Turbine Overspeed Block Trip DESCRIPTION:
During a review of administrative controls implementing TS Table 15.4.1-1 surveillances as part of U2R22 Startup item #,7, a calibratign procedure,'for the required annual (refuelin calibration of the turbine overspeed block trip could not be located. g)RT-4 O
(functional test) overspeeds.the turbine and records rpm when the mechanical trip actuates and directs operators to contact Maintenance if the trip is outside the This ORT-4 test may inadeauately meet the i
allowable rpm range.
galibration requirement of the turbine overspeed block trip, resulting in the violation of TS Table 15.4.1-1, Item 42.
Significance:
. Potential missed technical specification surveillance.
STATUS UPDATE:
DATE: 03/10/97 SCREENED BY :
REGULATORY REPORTABLE.... (
?: N TS VIOLATION.,
N1 N
I N
10 CFR 21.................i J: N TS LCO..........
OPERABILITY IMPACT PER TS. (
J: Y JCO REQUIRED.
N MSS REVIEW................(
l-N SCAQ.......
N OPERABILITY DETERMINATION.t
): N COMMITMENT...
N 1
SUPPORTING DETERMINATIONS-This has been identified.as a possible missed technical specification surveillance due to a missed calibration of the overspeed trip testing ot the turbine.
At this point it appears the testing is cor..pleted as part of an I+C callup however a full evaluation is needed to determine ifth:sitemistruly,amissed,surveillanceandthusreSmmediate uires an LER.
This..s gurrently ongoing.
At this point there are no operability or reportability concerns.
REFERENCES:
NPL 97-0048 ICP-10.16
- TRENDING INFORMATION:
FIRST QUARTER OF 1997 WHEN NON-OU1 AGE WHO
OPERATIONS I
INSTRUMENTATION AND CONTROL MAINTENANCE I
WHY
ADMINISTRATIVE CONTROLS (SPAC) WERE CONFUSING OR INCOMPLETE WHAT~~~ : INSTRUMENTATION AND CONTROL PERIODIC MAINTENANCE REGULATORY DOCUMENT - TECHNICAL SPECIFICATION RELATED
~~
INSTRUMENTATION AND CONTROL PROCEDURE ELECTRICAL INSTRUMENTATION OR CONTROL DEVICES SYSTEM: TURBINE RELATED ACTIONS PRI ACTION STATUS RESPONSIBLE PERSON DUE DATE
~~~~{~~~~~2[hh~~~~~kCTIbhhbbbbb
~
~~
~
~ '
~ '
'f$
5 d
ACTION ITEM STATUS REPORT PAGE 1
03/26/97
o****************************
Responsible Person:
Urgency: NO DUE DATE ASSIGNED
Trk$d: CR 97-0723 Work Priority: -100
Action Number:
1
eo*************************
Activity Pending is: ACTION NEEDED

TITLE AND TASK DESCRIPTION----------------------------

Turbine Overspeed Block Trip Determine if the turbine overspeed block trip testing is completed in and if the acccrdance witn the technical specification requirementsif ves, ensure technicgl specif:. cation requirements have been missed.
appropriate LCO _s entered and that the testing'notis completed within the If provide the techniqal specification allowed timeframe.the testing perfo,rmed conforms with Justification for responding that Make recommendations for action as technical specification requirements.
appropriate.
(per 3/6/97 morning meeting discussions)

Correction ******

Sour e Record:__.--DATES- /04/97
Evaluation *********
03 Comm tment:
Eval Due:
Corr Act Due:
Action Create: 03/10/97 Orig Eval Due:
Orig CA Due:
Action Closed:
Eval Done:
Corr Act Done:
__________ PEOPLE---------
Responsible for Overall Actign:
BMS Res onsible for Current Pending Activity: BMS Isg 9 Manager:
In1 lator:
Punchlist Administrator:

UPDATE--

(03/1G/o7 Received Action into Group: BMS Responsible Person:
....--- --REFERENCES-------
NPL 97-0048 ICP-10.16

MISCELLANEOUS------- ------------ S stem:

TU Originating Agency:
N C Status:
NRC Open Item Nueer:
Related Outages:
Engineering Work Type: Evaluation Person Hours:
Original Estimate =
Current Estimate
=
Actual Hours
=
i t
l l
CONDITION REPORT CR 97-0724 1
STATUS: OPEN UNIT: 1 SYSTEM: 125VDC INITIATED: 03/04/97 cincED:
MSS #:
ADMINISTRATOR:
INITIATOR:
ISSUE MANAGER:
NUMBEF OF OPEN ACTIONS:
1 NUMBER OF CLOSED ACTIONS:
0 Operation Of Emergency Lighting DESCRIPTION:
During a review of administrative controls implementing emergency power system Technical Spegifications as part of U2R22 Startup Item #7,byit was 16entified that the intent of TS 15.4.6.A.3 may not be satisfied plant procedures.
Specification 15.4.6,A.3 requires the proper including the automatic transfer switch-operationofemergencylighting,ddurin$5.4.6,A.3 state, for DC lichts to be demonstrate each reactor shutdown for a ma or fuel reloading, The bases to TS DC emergency i
li hts are provided in certain safeguards equipment areas which must be at ended to during a loss of all AC power.
The emergency lighting test provides DC power to the DC emergency lights.E'erates properly and verifies that the automatic transfer switch o However, ORT-3 ORT-3A, wbich may not meet the ? ion of DC lighting only in the control, room, a7d ORT-3B verify opera intent of the TS 15.4.6.A.3.
Siginficance:
Potential missed technical specification surveillance.
STATUS' UPDATE:
DATE: 03/10/97
- SCREENED BY :
REGULATORY REPORTAuLE.....
N TS VIOLATION.....
(Y/N N
10 CFR 21.................
N TS LCO........
.(Y N
l OPERABILITY IMPACT PER TS.
N JCO REQUIRED.
.(Y N
.(Y N
MSS REVIEW................
N SCAQ........
OPERABILITY DETERMINATION.
N COMMITMENT..
(Y
N SUPPORTING DETERMINATIONS:
This CR describes a situation where the testing performed for the emergency DC light 4ng may not meet the full intent of the Technical Specification rqquired test.
The tests are being evaluated at this time to determine this,and will be completed prior to any revisions to the tests or reportability statements.
It is unknown if the tests meet the full intent at this time, however it is believ d thag DC li hts areboimmediate testedapegautelytosatisfyQhetechnicalSpec$fications.
this time.
operability or reportability issues exist at
REFERENCES:
~
NPL 97-0048
. TRENDING INFORMATION:
I.WHEN--: FIRST QUARTER OF 1997 NON-OUTAGE OPERATIONS WHO MECH AND ELEC MAINTENANCE WHY
ADMINISTRATIVE CONTROLS (SPAC) WERE CONFUSING OR INCOMPLETE
- WHAT
REGULATORY DOCUMENT - TECHNICAL SPECIFICATION RELATED ELECTRICAL EQUIPMENT RELATED SYSTEM: 125 VDC-ELECTRICAL ACTIONS PRI ACTION STATUS RESPONSIBLE PERSON DUE DATE
~~~~~~ ~~~
~ ~ ~ ~ i ~ ~ ~ ~ ~ ~ { h 6 ~ ~ ~ ~ ~ [bT i bb ~ hbbb bb ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ '..~ ~..~
=A
ACTION ITEM STATUS REPORT PAGE 1
03/26/97 Responsible Person:
Urgency: DUE IN 16-30 DAYS
Trkid: CR 97-0724 Work Priority: -100
Action Number:
1 eeooce*************************
Activity Pending is: ACTION NEEDED

TITLE AND TASK DESCRIPTION------------------------------------------

, Operation Of Emergency Lighting 1
Determine if the Technical Specification requirements for testing the emergnecy DC lighting system are being satisfied by the current,Eesting proc 9 ures, and provide Justification for not missing the Technical d
S acification required surveillance.
If determined to be missed s rveillance ensure appropriate LCO is entered, testing is performed l
w thin the re, quired timeframe, and the appropriate procedures are revised.
Provide recommendation for further actions as deemed appropriate.
(per 3/6/97 morning meeting discussions)
Sourfe-Record:---DATES---- /97
Evaluation *********
Correction ******
03/04 Comm tment:
Eval Due:
Corr Act Due: 04/15/97 Act$on Create: 03/10/97 Orig Eval Due:
Orig CA Due:
04/15/97
)
Action Closed:
Eval Done:
Corr Act Done-1
_________. PEOPLE-------------------------------------
Responsible for Overall Action:
EIS Responsible for Current Pending Activity: EIS Issue Manager:
Initiator:
Punchlist Administrator:
1

UPDATE--------------------------------------------------------------

Responsible Person:
~~~~~
EIS (03/11/97 Received Action into Group:
Due Date: 04/15/97
,.(03/11/97.. J This item was discussed with Ops /MTN and there are other call-ups that actually do verify the functionality of the lighting.
Please verify and document
---REFERENCES---------------
NPL 97-0048

MISCELLANEOUS----------------------

i Originating Agency:
S stem:
125VDC JNRC Open Item Nuder:
N C Status:
Related Outages:
Engineering Work Type: Evaluation Person Hours:
Original Estimate =
l Current Estimate
=
Actual Hours
=
a ys -
.~
CONDITION REPORT CR 97-0725 STATUS: OPEN UNIT: 1 SYSTEM: MS INITIATED: 03/04/97 CLOSED:
MSS #:
ADMINISTRATOR:
~ ~ ~.
INITIATOR:
ISSUE MANAGER:
NUMBER OF OPEN ACTIONS:
1 NUMBER OF CLOSED ACTIONS:
0
' Main Steam Stop Valve Closure Timing DESCRIPTION:
During a review of administrat 4ve controls implementing main steam system valve T9chnical Specifications as aprt of U2R22 Startuo Item #7, it was identified that procedures TS-39, TS-40 and IT-280, 28DA, 2806, 4
285, 285A, and 285B may inadequa?ely measure the main s?eam stop, valve closure times.
TS 15.4.7.A requ4res closure times of five seconos or less measured from the time of signal initiation until the valve indicates closed.
However the controlling procedures meausre the time l
of the control room switch,or test buttons close signal to valve closure.
response time as discussed,This method does not include instrumentwhich may result in less 1n th9 bases to TS 15.4.7 conservative main steam stop valve c,losure times.
Significance:
Potential missed technical specification surveillance STATUS UPDATE:
DATE: 03/10/97 SCREENED BY :
REGULATORY REPORTABLE.....
N TS VIOLATION..............
): N 10 CFR 21..................
N TS LCO....................
J: N OPERABILITY IMPACT PER TS.
N JCO REQUIRED..............
J : N MSS REVIEW................
N SCAQ......................
J : N OPERABILITY DETERMINATION.
N COMMITMENT................
J: N SUPPORTING DETERMINATIONS:
is bel 1 ved the current testing adequatelv tests the closure times i
It 9
for the Main Steam Stop valves, however further review and evaluation of the procedures is warranted to ensure no missed surveillances have occurred.
Therefore, no immediate operability or reportability items are believed to exist for this item at this time.
REFERENCES:
NPL 97-0048 1
TRENDING INFORMATION:
WHEN
FIRST QUARTER OF 1997 NON-OUTAGE WHO
OPERATIONS WHY
ADMINISTRATIVE CONTROLS (SPAC) WERE CONFUSING OR INCOMPLETE WHAT- : REGULATORY DOCUMENT - TECHNICAL dPECIFICATION RELATED j
OPERATIONS PROCEDURE
~~
MECHANICAL CHECK VALVE RELATED SYSTEM: MAIN, EXTRACTION, GLAND SEAL, and REHEAT STEAM ACTIONS PRI ACTION STATUS RESPONSIBLE PERSON DUE DATE
\\
1
-100 ACTION VERIFICATION 03/21/97 i
-3 7
J
ACTION ITEM STATUS REPORT PAGE 1
03/26/97 Responsible Person:
Urgency: NOT DUE / IN CLOSEGUT
Trkid: CR 97-0725 Work Priority: -100
Action Number:
1 Activity Pending is: ACTION VERIFICATION

TITLE AND TASK DESCRIPTION-- ------- ----------------------- - - -

' Main Steam Stop Valve Closure Timing Determine if the current testing adequately addresses the requirements found :.n the Technical Specificationa and if a missed surveillance has in fact occurred.
Provide lustification 4f determined not to be a missed If determined to be a missed surveillance,he required TS ensure surveil:.ance.
testing is completed within t approprnate LCO is 9ntered, t1meframe, and provide recommendations for corrective action to prevent recurrence.
(per 3/6/97 morning meeting discussions)

DATES-------------------- luation *********

Correction ** ***
Sour e Record: 03/04/97
Eva Comm tment:
Eval Due:
Corr Act Due: 03 21 97 Action Create: 03/10/97 Orig Eval Due:
Orig CA Due 03 21 97 i
Action Closed:
Eval Done:
Corr Act Done:03 17 97 PEOPLE--------------------------------------
Respons$ble for Overall Action:
EIS Responsible for Current Pending Activity: SI Issue Manager:
Initiator:
Punchlist Administrator:

UPDATE-------

(03/11/97 Received Acrinn into Group: EIS Due Date: 03/21/97 Responsible Person:
(03/12/97 Passed to for acceptance of work.
(03/17 Passed to __.._.._
for Verification.
Review /97 '
of Td 13.4.7.A shows that the closure time (for the main steam line
' isolation valves) of five seconds or less shall be verified and the five seconds shall be measured from the time of sianal initiation until the valve indicates closed.
The basis of the TS states that a closure time of 1
-f4ve seconds was selected as being consistent with the expected response time for instrumentation as detailed in the steam line break incident analysis.
This may be interpreted to mean that the five seconds includes instrumentation response time.
Review of FSAR 14.2.5 for Rupture of a Steam Pipe is not conclusive as to whether the five seconds does or does not include instrument response time.
The F AR analysis does state that are} lies that, designed to close in the fast acting steam line isolation valves
(
imp the actuating less than 5 seconds with low flow).
The FSA injection (SI) actuation a:.gnal for steamline isolation is the safet" formation in the FSAR to s :.gnal.
However, there is no definitive in supportthis.
Review of Accident Analysis Basis Document DBD-T-35 Volume 4, Module 12, Rev. O for the Rupture of a Steam Pipe on page 12-2$ under Engineered Safeguards Features, Steamline Isolation states:
"A total response time of 7 seconds is assumed from the time the,setpoint is reached until completionof closure of the steamline isolation valves.
This response is generally broken down as a 2 second allowance for signal orocessing (Ref.
and 5 seconds for valve closure (Ref. 12.7-21) the does not model this specific breakdown for the;chcwever, response time and analysis) 12.7-21 therefQre only forces a requi.rement on the total time to complete the solation function " Review of the specific cases of the accident that niticte the steamline isolation functionin th(note:
there are two cases that o not initiate steam line isolat$on) e DBD Table 12-4 shows that the SI sianal,for the sQeamline isolation.in concert wiqh high-high steam flow, is the initiating actuation From the time that the SI actuntion setpoint is reached o the SI actuation is 2.0 seconds and from the SI actuation to the Steaml ne Isolation is 5.0 seconds.
Althouah the DBD, stated time is for 7 secon s from reaghing setpoint until isolation valve closure, the actual case studies utilize the 2 and 5 second requirements.
Therefore,' DBD shows that the.five second closure time of the main steam
JACTION' ITEM STATUS REPORTL PAGE 2
03/26/97 isolation valve is in fact.the time from signal initiation'to valve clonureand does not include instrumentation response time.
Present
.tecting substitutes 1the SI contact closure..th a manual switch contacQ clo-ure, which is an acceptable substitut9 tor the initiation signal since i
$imIna is-started from throwing of the switch.
The full closurg time includes steaml$ne isolation relay p$ckuo valve circuit actuation and valve stroke.This is fully embodied in the, TS requirement-and the present the present testing meeps the TS requirement and
-testing.-Therefore there'is no TS violation and no need to revise the testing based,upon this concern.
However, it is recommended-that the wording in the TS basis be revised to e;.iminate the words " time for instrumentation" so that the basis reads, "A
-c..osure time of five seconds was selected as being consistent with the expected response as detailed in the steam line break incident analysis. "-
This w:.1:
more accurately reflect tne actual analysis and eliminate any
, potent: a:
misunderstanding about instrument. response time.
.This action item may be closed.

REFERENCES-----------------------------------------------

NPL 97-0048

MISCELLANEOUS------------------------ ------- MS

'. Originating Agency:
System:
NRC Open-Item Number:
NRC Status:
, Related Outages:
Engineering hork: Type: Evaluation
, Person Hours:
Original Estimate =
Current Estimate
=
Actual Hours
=
4
)
\\
j-a= L.
CONDITION REPORT CR 97-0726 STATUS: OPEN
' UNIT: 1 SYSTEM: VNCC INITIATED: 03/04/97 CLOSED:
MSS #:
ADMINISTRATOR:
XNZTIATOR:
0 ISSUE MANAGER:
NUMBER OF UFEN ACTIONS:
2 NUMBER OF CLOSED ACTIONS:
0 Containment Fan Cooler Accident Fan Test DESCRIMION :
During a review of administrativg controls implementing ECCS and
-containment coolin system Technical Specifications as part of the U2R22 Startup Item #7 i
was identified that procedures TS-33 and TS-34 may not be adequately mplementing TS 15.4.5.I.C.2.
TS 15.4.5.I.C.2 requires conta:.nment fan cooler accident fans to be operability tested monthly to vernfy that the accident fan starts and the running current is acceptablg.
However, TS-33 and TS-34 only starts fans that are not already running and measures the running current of those fans.
Fans that are alreadv runnina ar9 not stopped and then started.
Therefore, all fans may not be tesEed in accordance with TS 15.4.5.I.C.2.
Sign;ficange:
Possicle. violation of missed surveillance Technical.
Spec:.f ica tions.
i Corrective action taken:
Declared that a TS surveillance was missed and commenced the testing of the fans.
The testing was completed satisfactorily at 0403 on 3/5/97.
1 i
STATUS UPDATE:
DATE: 03/06/97 j
SCREENED BY :
REGULATORY REPORTABLE.....
?: N TS VIOLATION..............
?: N 1
10 CFR 21..................
J: N TS LCO....................
J: N OPERABILITY IMPACT PER TS.
J: Y JCO REQUIRED..............
J : N N
SCAO......................
J : Y MSS REVIEW................
JN COMITMENT......
J: N OPERABILITY DETERMINATION.
J:
SUPPORTING DETERMINATIONS:
This CR was determined to be a missed Tech Soec Surveillance and the-appropriate action statement was entered.
The fans were retested within tne allowed 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months peiod and the fans declared operable.
This will require an LER due to a missed TS surveillance.
No further operability or reportability issues exist at this time.
j 1
REFERENCES:
TECH SPEC 15.4.5.I.C.2 NPL 97-0048
-TRENDING INFORMATION:
WHEN
FIRST QUARTER OF 1997 NON-OUTAGE 1
WHO
OPERATIONS WHY
SITUATION WAS NOT COVERED BY PROCEDURE WHAT
REGULATORY DOCUMENT - TECHNICAL SPECIFICATION RELATED PROCEDURAL PROBLEM MECHANICAL FAN RELATED SYSTEM: CONTAINMENT COOLING H AND V ACTIONS PRI ACTION STATUS RESPONSIBLE PERSON DUE DATE 1
-100 RECEIVE ASSIGNMENT 2.
-100 RECEIVE ASSIGNMENT 3-vg 9%
. ACTION ITEM STATUS REPORT PAG 1
03 26/97 eo*****************************
Responsible Person:
Urgency: NO DUE DATE ASSIGNED
'Trkid: CR 97-0726 Work Priority: -100
Action Number:
1
eeeeee*************************
. Activity Pending is: RECEIVE ASSIGNMENT

TITLE AND TASK DESCRIPTION----------------------

Containment Fan Cooler-Accident Fan Test Revise TS-33 and TS-34 to ensure that all containment fan cooler accident fans are tested in accordance with Technical Specification 15.4.5.I.C.2.
Sour e Record:----------DATES----
/97'
* ***** Evaluation *********
Correction ******
03/04 Comr tment:
Eval Due:
Corr Act Due:
ActLon Create: 03/06/97 Orig Eval Due:
Orig CA Due:
ActLon Closed:
Eval Done:
Corr Act Done:

PEOPLE--------------

Responsible for Overall Action:
OPS Responsible for Current Pending Activity: OPS Issue Mana Initia or:ger:
Punchl st Administrator:
......----UPDATE---------------
.......---REFERENCES-----------------------------------------
TECH SPEC 15.4.5.I.C.2 NPL 97-0048

MISCELLANEOUS----------------------

Originating Agency:
S stem:
VNCC NR en Item Number:
N C Status:
Re d Outaaes:
Eng neering Work Type: None,Specified Person Hours:
Original EsQ1 mate =
Current Estimate
=
Actual Hours
=
'9 e."
J,j
+
ACTION ITEM STATUS REPORT PAGE 1
03/26/97 Responsible Person:
Urgency: NO'DUE DATE ASSIGNED
Trk4d: CR 97-0726 Work Priority: -100
Action Number:
2
- e**e***************************
Activity Pending is: RECEIVE ASSIGNMENT

TITLE AND TASK DESCRIPTION-------- ------------------------- ------

Containment Fan Cooler Accident Fan Test Develop an LER for the missed Technical specification surveillance concerning the containment fan cooler accident fan testing.
- (per 3/5/97 morning meeting discussions)
Sourge Record:----------DATES----
/97

ion ******-

Correct
Evaluation ********* ******Act Due:
03/04 Corr Commitment:
Eval Due:
Action Create: 03/06/97 Orig Eval Due:
Orig CA Due:
Action Closed:
Eval Done:
Corr Act Done:
...-------PEOPLE------
Responsable for Overall Action:
9I Responsnble for Current Pending Activity: SI Issu Manager:
Init or:
Punc st Administrator:
I
___-------UPDATE-------------------
(03/07/97 Issued en Grnoo: SI Outstandina item from TS Admin Control review.
Please assign to -
with a April 4,-1997, ue date.
i
. ___..-----REFERENCES----------------------------------------------------------
TECH SPEC 15.4.5.I.C.2 NPL 97-0048
______.-MISCELLANEOUS---------------- --- S stem:
VNCC Originatin Agenc :
NRC O n I em Nu er:
N C Status:
Relat Quta es:
- Engineering ork Type: None Specified Person Hours:
Original Es(imate =
Current Estimate
=
Actual Hours 1
=
i i
a
/
0 4
l
CONDITION REPORT CR 97-0727 STATUS: OPEN UNIT: 1 SYSTEM: FP INITIATED: 03/04/h?
FLn9ED:
MSS #:
ADMINISTRATOR:
INITTATOR:
1 ISSUE MANAGER-NUMBER OF OPEN ACTIONS:
2 NUMBER OF CLOSED AC11UNS:
0 Quarterly Diesel Dr'iven Fire PumpEngine Fuel Sample Analysis
' DESCRIPTION:
During a review of administrative controls implementing #7, fire protection
-Technical Specifications as part of U2R22 Startup Item it was identified that the diesel fire pump day tank (T-30) is not sampled durino performance of TS-80.
This may be in violation of Technical 1
Specification 15.4.15.A.1.d.2 which requires a quarterly diesel driven fare pump fuel sample analysis.
. Significance:
Potential missed Technical Specification surveillance.
Corrective action taken:
The applicable action statement of technical specifications was entered, the test sample was taken and sent to an independent lab for analysis.
1 STATUS UPDTTE:
DATE: 03/06/97 SCREENED BY :
REGULATORY MEPORTABLE.....(
N TS VIOLATION..............
N 10 CFR 21.................
3
N TS LCO.........
N OPERABILITY IMPACT PER TS.(
Y JCO REQUIRED..............
N MSS REVIEW................(
N SCAQ......................
Y OPERABILITY DETERMINATION.UY
N COMI TMENT.........
Y i
SUPPORTING DETERMINATIONS:
This was determined to be a missed Technical Specification surveillance The samole anal sis is being performed and is therefore LER reoortable.
and the results are to be back within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .
M.he appropriate action statement was entered, and the fire pump declared inoperable until the' reportability requirements associated with this CR.perability or return of the test results.
There are no further o
REFERENCES:
NP 97-0048 TS 15.4.15.A.1.D.2 TRENDING INFORMATION:
-~: FIRST QUARTER OF 1997 WHEN NON-OUTAGE WHO
OPERATIONS WHY
SITUATION WAS NOT COVERED BY PROCEDURE WHAT-~: REGULATORY DOCUMENT - TECHNICAL SPECIFICATION RELATED 1
-~
PROCEDURAL PROBLEM i
MECHANICAL TANK OR PRESSURE VESSEL RELATED CONSUMABLE OR REPLACEMENT PARTS RELATED SYSTEM: FIRE PROTECTION ACTIONS PRI ACTION STATUS RESPONSIBLE PERSON DUE DATE 1
-100 RECEIVE ASSIGNMENT 2
-100 ACTION NEEDED 04/04/97 d
k 4
e, #
\\
-ACTION ITEM STATUS REPORT PAGE 1
03/26/97
ce**************************
Responsible Person:
Trk:.d : CR 97-0727 Urgency: NO DUE DATE ASSIGNED Work Priority: -100
Act: on' Number:
1 eeoose*************************
' ASSOCIATED WITH A SCAQ ISSUE Activity Pending is: RECEIVE ASSIGNMENT ASSOCIATED WITH A COMMITMENT

TITLE JUID TASK DESCRIPTION------------------------------------------

Quarterly Diesel Driven Fire PumpEngine Fuel Sample Analysis Revis TS-80 to ensurg that the diesgl driven fire pumo day tank is sampi d and analyzed in accordance with the requirements of Technical Spsci ication 15.4.15.A.1.d.2.
Sour e Record:...--DATES- /04/97
Correction ******
03
Evaluation *********
Comn tment:
Eval Due:
Corr Act Due:
Act:.on Create: 03/06/97 Orig Eval Due:
Orig CA Due:
Act:.on Closed:
Eval Done:
Corr Act Done:

PEOPLE---------------------------------

Responsible for Overall ActiQn:
OPS Responsible for Current Pending Activity: OPS Issue Manager:
Initiator:
Punchlist Administrator-
.......... UPDATE---------------------
......... REFERENCES------------------ 5.A.1.D.2 NP 97-0048 TS 15.4.1

MISCELLANEOUS----------------------

Originating Agency:
S stem:
FP NRC Open Item Number:
N C Status:
Related-Outages:
Engineering Work Type: None,Specified Person Hours:
Original Estimate =
Current Estimate
=
Actual Hours
=
l
~
)
1 l
1
)
ACTION ITEM STATUS REPORT PAGE 1
03/26/97 coeeeeee***********************
Responsible Person:. DUE IN 1-1d UAYS
-Trk{d: CR 97-0727 Urgency:
Work Priority: -100
Act_on Number:
2 eeeeee*************************
ASSOCIATED WITH A SCAO ISSUE Activity Pending is: ACTION NEEDED ASSOCIATED WITH A COMMITMENT

TITLE AND TASK DESCRIPTION------ ------------------- --- -

l Quarterly Diesel Driven Fire PumpEngine Fuel Sample Analysis Prepare an LER for the missed Technical Specification concerning the diesel driven fire pump day tank sampling listed in TS 15.4.15.a.1.d.2.
Sour e Record:----------DATES- /04/97 Correction /04/97 03
Evaluation *********
Due: 04 Commitment:
Eval Due:
Corr Act Act:.on Create: 03/06/97 Orig Eval Due:
Orig CA Due:
04/04/97 Act..on Closed:
Eval Done:
Corr Act Done:
PEOPLE--------------------------------------------------------------
Responsible for Overall Action:
LRE Responsible for Current Pending Activity: LRE Isgue Manager:
Initlaqor:
1 Punchlist Administrator:
1
.---------UPDATE--------------------------------------------------------------
1 (03/07/97 I) Rece.4vad Action.into Group: LRE Responsible Person:
Due Date: 04/04/97 l

REFERENCES----------------------------

NP 97-0048 TS 15.4.15.A.1.D.2 i
.......---MISCELLANEOUS--------
1 Originating Agency:
System:
FP 1
~NRC Open Item Number:
NRC Status:
Related Outages:
. Engineering Work Type: None Specified Person Hours:
Original Estimate
=
Current Estimate i
=
i Actual Hours
=
i i
Y' gr A
"g q
p.
CONDITION REPORT CR 97-0?46
. STATUS: OPEN UNIT: O SYSTEM: XX INITIATED: 03/04/97
' ri. NARD :
i
' MSS #:
ADMINISTRATOR:
ISSUE MANAGER:
INITIATOR:
c._...~..
NUMBER OF OPEN ACTIONS:
1 NUMBER OF CLOSED ACTIONS:
0 Environmental Monitoring Checks May Have Been Missed DESCRIPTION:areviewofadministrativecontrolsimplementinh,TSTable Durin surveillances as part of U2R22 Startup Item #
it was 15.4.
-1 ident fled that monthly environmental monitor checks as required by TS Item 30 are no longer performed.
Radiological Table 15 4.1-1,icated tbat these checks are now being conducted Engineering ind quarterly In accordance with TS Table 15.7.7-1.
Significance:
Possible missed Technical Specification surveillance STATUS UPDATE:
DATE: 03/06/97 SCRE'7ED BY :
?: N TS VIOLATION.....
{*N nEGULATORY REPORTABLE.....
N 10 CFR 21.................
J: N TS LCO........
OPERABILITY IMPACT PER TS.
J.N JCO REQUIRED.
N MSS REVIEW................
J. N SCAO..........
N OPERABILITY DETERMINATION.(Y J: N COMMITMENT..
N SUPPORTING DETE.RMINATIONS: that needs to be res9 ved to determine if.there is 1
Thisisadiscrepancktechnigalspecificationsurveillance.
-It dges not-in actuali4y a misse cause any immediate coerability concerns for the units and there is nothing to indicate that it is recortable at this timg.
Further evaluation will be peformed to determing if the surveillance has been missed and determine the reporting requirements.
REFERENCES:
TS TABLE 15.4.1-1 TS TABLE 15.7.7-1 NPL 97-0048 TRENDING INFORMATION:
WHEN
FIRST QUARTER OF 1997 NON-OUTAGE
'WHO
HEALTH PHYSICS WHY
AWAITING FURTHER EVALUATION TO DETERMINE ROOT CAUSE WHAT- : REGULATORY DOCUMENT - TECHNICAL SPECIFICATION RELATED HEALTH PHYSICS PROCEDURE SYSTEM: NOT SYSTEM RELATED i
ACTIONS PRI ACTION STATUS RESPONSIBLE PERSON DUE DATE 1
g j
ACTION ITEM STATUS REPORT' PAGE I
Responsible Person:
Urgency:'DUE IN 1-15 DAYS
Trk$d: CR 97-0746 Work Priority:
9
Action Number:
1 i
eee*************************
Activity Pending is: ACTION NEEDED

TITLE AND TASK DESCRIPTION------------------------------------------

Environmental Monitoring Checks May Have Been Missed Evalute the dicrepancy in the technical specification tables and determine if there has been a missed technical specification surveillance.
be determined that a missed-surveillance has occurred.quirements should it Interface,with Licensing to determine the reporting re
..---DATES---- /97
Correction /28/97 Sour e-Record: 03/04
Evaluation *********
1 Corr Act Due: 03 l
Comm tment:
Eval Due:
Action Create: 03/06/97 Orig Eval Due:
Orig CA Due:
03/28/97
)
Action Closed:
Eval Done:
Corr Act Done:

PEOPLE--

Responsible for Overall Action:
CHE Responsible for Current Pending Activity: CHE Issue Manager:
Initiator:
Punchlist: Administrator:
I UPDATE--------------------------------------------------------------
(03/07/97 Received Action into Group: HP l
Responsible verson:
Due Date: 03/28/97 1
(03/07 Set Work Priority to 9.
This item involves a change in the environ /97 mental monitoring program where hi i
were eliminated from the program in 1975.gh pressure ionization enambers TS Table 15.4.1-1 item 30 was not updated to reflect this change. This may require a 30 day LER due to l
the missed surveillance, 1
I ged Responsible Group:ponsible Person:
Chan/10/97__. Ghanged Res From o
(03 From (HP) To (CHE).
Channad Da=9onsible section:
From (PRD) Tc (NES)..
Reassigned per reques t.
(03/17/97 This item concerns Item 30 of TS 15.4.1, Table 15.4.1-1, which reqaires a monthly check of environmental monitors. The basis for is that ' Failures in" upscale" or "do,wnscale" e indicators,as stated in TS 15.4.1, fa the check required by Item 30, i
fuses defectiv 1
such as blown instrument indication can be easily which result recognized by simple observation of the functioning of an instrument or I
system " This " check" currently is not being done by anyone.
The question has arisen as to whether not conducting the monthly check constitutes a Tc violation.
The two following questions have to be answered in order t:-
determine if a Techspec violation is involved.1
1. What is meant by an environmental monitor.
. Technical Specification 15.4.10, Operational Environmental Monitgring programis ouglin)ed in Section 2.8 of the FFDSARthe operation environmental monitoring (April 20, 1970 states that If further states that various locations to provide a means
gamma radnation chambers are used atof detectnnq significant changes in environmental radioactivity as the result of plant releases.
The pre-ooerational environmental monitoring program FFDSAR' Table 2.8-1) listed film badges at two locations which wera coll (ected monthly to measure integratea radiatign dosg around the p-ant.
Alater amendment tg the FFDSAR states that in addition to the pre-operatnonai..strayradiationchambersarealso,beinbeinggivento f
talm badges, employed for studies.. " and that " Consideration is incorporat:.ng TLD badges inQo the program. " Film badges with there
_nharent fading, had beene11m:.natea by the time of the hBNP Final Environmental Statement, submnttedto the AEC in May 19 The
" post-operational environmental radioactivity survey" 72.
is described as ihcluding monthly or cuarterly TLDs and ion chambers. The May 30, 1973 FFDGAR, Table.2.B-2 cIarifies that there are twosets of TLDs: one set is rsaa monthly, the other quarterly.
Results from these three sets of environmental ra,diat ion chambers _3nd two sets of are reporued-in the Sem$on measurements,lannual monitoring reports unt11 the cmbient
TuD, Jcnuary-July 1976 report and in the previous Operation Reports.
Ion i
ACTION ITEM; STATUS REPORT PAGE
'2 03/26/97 chamber and monthly TLD resu3ts are not reported in subsequent monitoring reports.
' Based on the frequency, th'e referenced monthly checks can only refer to either the monthIv TLDs or the monthly ion chambers.
However, based on thebasis statement:for the monthly check TLDs can be eliminated because TLDs have not have fuses or amplifiers which would require checking as describedin t he TS 15.4.1 Basis Statement.
This is further supported by a WE letterto Mr. John E.
Stolzenberg by R; P.
Rouse in reply to questions about the PBNP low-level radioactivity in the vicinity ot PBNP that
. radiation chambers are the only part of the environmental analyses that are-read by-plant personnel 2.
HDo the missed monthly checks constitute a TS violation?
it is conclude that the monthl
checklistedinItemSertinentdocuments o of Table 15.4.1-1 in TS 15.4.1 is an item which.y Based on a' review of wasmistakenly not removed when TSCR No. 26 was submitted.
The following outlines the' sequence of events which lead to this conclusion.
In a January 24 1975 memo to Glenn Reed PBNP plant manager, E.
J.
Lipke documents the re, view of the radiological, environmental monitoring nrogram requested by Mr. Reed The review recommends eliminating the monthly TLDs as redundant and a hoidover from,the old days of film badges.
It also recommends the phase out of the ion chambers.
Furthermore, the review recommends that an Environmental Manual be written to contain all of the requirements for the radiological environmental monitoring program instead of relying on numerous documents such as the FFDSAR and procedure HP-11A.
The monthly ion chambers and TLDs are not listed as part of the gadtological environmental monitoring program in Rev. O of the 1975.
In the Lipke to Reed memo Envaronmental Manual dated September,l of a change to the radiological 1975 MSS approva datad September 22, i
environmental monitoring, program is requested.
The draft of the tech spec change request letter soecifically states that radiation chambers, i.e.
thestray radiat4on chambers or ion chambers mentioned in FFDSAR Table 2.8-1 _are eliminated. Technical Specification Change NO. 26 submitted on Octobe,r 10, 1975 also states in the cover letter that the radiation chambers are eliminated from the program.
Also, Table 15.4.10-1 of the submitgal wnich delineates the program only lists quarterly TLDs for After
' measuring tae gamma dose in the environments around PBNP.
(on July 12 and August 12 1976) in additional material was supplied response to comments by the NRC, none of which concerned elimination of the monthly TLDs and ion chambers written NRC approval for TSCR 26 was Tbe ap Therefore, proved monitoring program did not granted on Sep$ ember 23 1976.
2nclude radiation chase,rs.
it is concluded that the mention of monthly checks of environmental radiation in TS Table 15,4.1-1 is an item which inadvertentlWas not removed from TS for TSCR #26 in 1975 and was 1 superseded by the NRC approval of the program submitted by the TSCR request.
Thergfore not conducting the monthly checks of environmental monitors in this table does not constitute a violation of technical specifications because the items towhich Item 30 of the TS refers to were eliminated by a previous TS change.
(03/17/97 Passed to for acceptance of work.
........... REFERENCES--------------------------------
'TS TABLE 15.4.1-1 TS TABLE 15.7.7-1
'NPL 97-0048
..w.....---MISCELLANEOUS---------------------------
! Originating Agency:
System:
XX NRC Status:
'NRC Open IEem Number:
Emlated ou;egesit Engineering work Type: None,Specified Person Hours:
Original Estimate =
Current Estimate
=
Actual Hours
= 40 m
CONDITION-REPORT CR 97-0766 STATUS: OPEN UNIT: 1 SYSTEM: VNCR INITIATED: 03/04/97 CLOSED:
' MSS #:
' ADMINISTRATOR:
~
IMITXATOR:
ISSUE MANAGER:
NUMDER OF OPEN ACTIONS:. 1 NUMBER OF CLOSED ACT1Uno.
O Control Room Emergency Filtration Testing
DESCRIPTION:
During-a review of administrat ve controls implementing control room 4
emergency filtration Technical Specifications as part of U2R22 Startup Item #7, it was identified that TS 15.4.11.4 may not be adequatelv implemented by plant procedures.
Health Physics procedure HPIP-li.54 was the only procedure that could be locatea which controlled the testing of TS 15.4.11.4, control room emergency filtration gompone m.,
This procedure does ngt,contain acceptance criteria, there is no reference to th9 required HEPA and charcoal absorber tests after 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months of operation and after painting, fire or chemical release in the there is no reference to the required cold DOP tests after control room, eagh complete or partial replacement of HEPA filters or afetr structural maintenance to the filter housing, and there'was no reference to the required fan test after 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months of operation and following fan maintenance.
Indications are that the fans are tested on an annual basis in March.
Significance:
Potential for missed Technical Specification surveillances.
STATUS UPDATE:
DATE: 03/11/97 SCREEMED BY REGULATORY' REPORTABLE.....
N TS VIOLATION..............
?.N 10 CFR 21.................
N TS LCO....................
J: N OPERABILITY IMPACT PER TS.
Y JCO REQUIRED..............
J.N MSS REVIEW................
N SCAQ......................
J.N OPERABILITY DETERMINATION.
N COMMITMENT..
?-
N SUPPORTING DETERMINATIONS:
This is a question as tg whether the technical specification surveillance has been missed.
At this point, through conversations with HP, it does not appear as though any TS surveillances have been missed.
However, further evaluation will be perfcrmed to ensure this is the at this No immediate operability or reportability concerns exist case.
time.
REFERENCES:
NPL 97-0048 l
TRENDING INFORMATION:
WHEN
FIRST GUARTER OF 1997 NON-OUTAGE WHO
OPERATIONS HEALTH PHYSICS WHJ
ADMINISTRATIVE CONTROLS (SPAC) WERE CONFUSING OR INCOMPLETE WimT
HEALTH PHYSICS RELATED REGULATORY DOCUMENT - TECHNICAL SPECIFICATION RELATED HEALTH PHYSICS PROCEDURE MECHANICAL FAN RELATED SYSTEM: CONTROL ROOM HVAC ACTIONS PRI ACTION STATUS RESPONSIBLE PERSON DUE DATE
~
r 04/04/97
,,-1 e52 3 7.CTION r.NEEDED i
k
\\
ACTION ITEM STATUS REPORT PAGE 1
03/26/97 ce*****************************
Responsible Person.
Trkid: CR 97-0766 Urgency. vuE IN 1-15 DAYS Work Priority:
52
-Action Number:
1 Activity Pending is: ACTION NEEDED

TITLE AND TASK DESCRIPTION---------

Control Room Emergency Filtration Testing Determine if the current testina procedures have caused a missed Techn:ca'.
Specification surveillance for the control room emergency filtration avstem.
If yes, ensure the proper technical Specification action statement is entered and the testing completed within the required timeframe.
If not, provide justifcation for not missing the TS curve 111ance, and provide recommendations for corrective / improvement actions as appropriate.
(per an 3/10/97)
Sourge Record:----------DATES----
/97
Evaluation *********
Correction ******
03/04 Commitment:
Eval Due:
Corr Act Due: 04/04/97 Actnon Create 03/11/97 Orig Eval Due:
Orig CA Due:
04/04/97 Actnon Closed::
Eval Done:
Corr Act Done:

PEOPLE--------------------------------------------------------------

Respons$ble for Overall Actign:
HP Responsiale for Current Pending Activity: HP Icsue Manager:
Initiator:
Punchlist Administrator:
.-------.-UPDATE-------------------------
(03/12/97 Received Action into Group: HP Responsible Person:
Due Date: 04/04/97
~"
(03/12/97
. Set Work Priority to 52.
Failure to adequatelv perform tech pec rgauired testing of the control room ventilation filters could quest 9n ab1Iity of the, system to operate properly during accident condi lons and may require an LER.

.-----REFERENCES----------------------------------------

NPL 97-0048

MISCELLANEOUS-------

Originating Agency:
S stem:
VNCR NRC Open Item Number:
N C Status:
Related Outages:
Engineering work Type: None,Specified Person Hours:
Original Estimate =
Current Estimate
=
Actual Hours
=
1-i.
J
CONDITION REPORT CR 97-0831 r
STATUS: OPEN UNIT: 0 SYSTEM: XX INITIATED: 03/11/97 CLOSED:
MSS #:
ADMINISTRATOR: '
INITYATOR:
tVER ISSUE MANAGER:
NUMBER OF OPEN ACTIONS:
4 NUMBER OF CLOSED ACTIONS:
0 Procedures Have Missing Incorrect And/Or Inconsistent References To technical Specifications, i
DESCRIPTION:
Many procedures have missing incorrect, and/or
==
Description:==
inconsistent reterences to Technical Specifications A review of administrative controls implementing Technical Specifications as cart of U2R22 Startup Item #7 identified many orocedures imolementing Technical S ecifications that have inadequate references to the associated T chnical Specifications.
The following procedures contain d screpancies: Engineerina 1.
RESP 3.1, Step 5.14.1, needs more specific TS references for restrictions with both RCPs deenergized 2.
RESP-4.2 should reference TS Table 15.4.1-2 Item 9b 3.
IT-510B + 515B Step 1.2 should reference TS Table 15.4.1-2 Item 22 rather than Item 24
4. IT-545B (Containment spray) should reference TS Table 15.4.1-2 Item Steps 4.2.36 and 4.3.36 and IT-3A + 4A Steps.4.2.11 22 5.
IT-01 + O2, 4.3.13 and 5.4 reference the Operations, Standing Order a,s containing,
pumpand, valve op,erability criteria. There is no longer an Operations Standing Order book.
Operations 1.
CL-1A should reference the individual Specifications implemented (as in CL-1D).
2.
CL-1D, Steps 2.5 and 3.5, should also rererence TS 15.3.1.D.3 15.3.1.F,.4 4.p 3.31, should reference TS 15.3.1.F.5 rather than TS
3. CL-1D Ste CL-1D should reterence 15.3.6.A.1 rather than OM-4.S. Step 2.24,k, boric acid system piping temperatures 5:
"Chec 15 6.3.A.a 5.
(all > 145 F)houlo check storage tank and piping temperaturessyrveillancerequirement of temperatures
> Table incorrect -s 15.3.2-1 temperature.
Also TS reference should be Table 15.4.1-2 Item 4
.20 rather than Item 21.
"6 heck waste distillate tank discharge flow
" TS reference should be Table 15.7.4-1 Item 1.d rather than meter...,7.4-2 Item 1.d Table 15.
~
All references to TS Section 15.4.4 are incorrect
" BAST isolation valves " should reference TS 15.4.5.II.B.2 rather than TS15.4.5.II.B.4
" Test boric acid piping heat tracing circuit operability," should be i
deleted.
"Verif isolation valves are locked shut."y containment purge supply and exhaust TS reference should be Table 15.4.1-2 Item 23 rather t aan Item 25 hFire suopression water system cumo capacity test,"
saould reference TS 15.4.15 A.1.c rather than 15.4.15,1.c "F2re 3
suppression water syptem flow test references nonexistent TS 15.4.15.A.5
" Containment fa cooler units," should reference TS 15.4.5.I.C.1 "Accumulatorcheckvalves," references nonexistent TS 15.4,5.II.B.3
" Evaluate integrity of post-accident recovery system should reference Table 15 4 Item 22 rather outside containment,lete cycle of PORV block valve.1-2 snould reference than Item 24
" Comp s,"
TS Table 7.5.4 1-2 Item 21a rather than Item 23
" Verify charaing oump i
operability,' should reference TS Table 15.4.1-2 Item 31 rather than Item 33
" Full stroke test of atmospheric steam dumps," should reference TS Table 15.4.1-2 Item 28 rather than Item 30
" Check 120 Vac instrument TS reterence shou /2035,ld be Table /2041) buses " should not r ference CR Shift Log (PBF-2034 2040 or CR CS6 LogItem 26 rath(er than-Also,ify crossover steam dump valve 15.4.1-2 PBF-2038 2039).
tem 28 "Ver operabilit TS reference should be Table 15.4.1-2 Item 29 rather than
~ Item 31 Derify 100 kW of PZR heaters'available " TS reference should be Tab:.e 15 4.1 2-Item 30 rather than Item 32 "herify operability of potentnal dilution in progress alarm," is referenge should be Table 15.4,1-2 Item 32 r5ther than Item 34
" Check iodine and particulate continuous air sampler on purge stack," should reference TS Table 15.7.4-2 Item 4.d r~ ather than Item 4.e 1.
TS 15.4.11.2+3 not referenced in TS-9 or ORT-3 2. TS Tgs(s related to fire suppression and detection 1
systems do not-have explicit references to the TS requirements they satisfV.
3, RMSASRB CI,RE-305 should reference TS 15.3,1.D.7 4.
PBF 1
Auxiliary Building Shift Log," Acid Heatshguld read " Boric Acid 2034, Temperature" rather than " Boric Tracing Recorder" for Piping Instrument TR-4177 Maintenance'1. ICP-4.27, Rev 10, Step 2.1.1, contains an erroneous
+ - -
w
reference to TS Table 15.4.1-1 Item 1 2.
RMP-9071, Rev 2, Step 2.1 should reference TS Table 15.4.1-1 Item 13 rather than Items 36, 30a and 37b-Q.,Mos$ RMPs contain no references to implemented Technical Specifications HP/ Chemistry 1. EPMP-1.1 and 1.2' should reference TS Table 15.4.1-1 Item
- 29 rather than Item 30 2. HPCAL-1.1 should reference Table 15 4.1-1 Item
' 29 rather than Item 27 3. HPIP-7.51 should refgrence the individual Specifications implemented Significance Violation of NP 1.2.1, Step 3.1, and NP 1.1.3, Step 5.1.2.
STATUS UPDATE:
DATE: 03/24/97 SCREENED BY :
REGULATORY REPORTABLE.....
): N TS VIOLATION.
N : N ERA I i' $Pd I"P5R'iSl 0 REQ R$.'
['"
I'
)
'1 N)
N MSS REVIEW................
/
N SCAQ.......
. sYcN N
OPERABILITY DETERMINATION.
J: N COMMITMENT, SUPPORTING DETERMINATIONS:
These are administrative dicrepancies between Technical Specificatioon and various procedures which are currently in use.
None of these discrepancies has lead to any components being classified as inoperaole or OOS.
They are all administrative in nature and will be reoaired through procedure revisions.
No immediate operability or reportability
^
issues are present at this time.
REFERENCES:
VARIOUS (SEE DESCRIPTION)
. TRENDING INFORMATION:
WHEN
FIRST QUARTER OF 1997 NON-OUTAGE
-~
WHO
OPERATIONS SITE ENGINEERlNG MECH AND ELEC MAINTENANCE
.l WHY
ADMINISTRATIVE CONTROLS (SPAC) CONTAINED A TECHNICAL ERROR WHAT~~~~:. REGULATORY DOCUMENT - TECHNICAL SPECIFICATION RELATED PBNP ADMINISTRATION PROCEDURE OPERATIONS PROCEDURE i
HEALTH PHYSICS PROCEDURE MAINTENANCE PROCEDURE SYSTEM: NOT SYSTEM RELATED ACTIONS PRI ACTION STATUS RESPONSIBLE PERSON DUE DATE
~~~
~~ ' ~
'~~
~~~~[~~~~~.~[ho~~~~~kkhkjVE~EUUibhkbhT 2
-100 RECEIVE ASSIGNMENT 3
-100 ACTION NEEDED 4
-100 RECEIVE ASSIGNMENT h'
a b
ACTION ITEM STATUS REPORT PAGE 1
03/25/97 Responsible Person:
Trkid CR 97-0831_
Urgency: NO DUE DATE ASSIGNED I
Work Priority:*-100
Action Number:
1
ee***************************
j Activity Pending is: RECEIVE ASSIGNMENT

TITLE AND TASK DESCRIPTION---------------------------

Procedures Have Missing Incorrect And/Or Inconsistent Reference. To
. technical Specifications, Review the procedur9s listed in tiie descript$on section of the CR parent record under Operations for adequacy of providing the correct references to Technical Specifications.
Make revisions to procedures.as necessary.
(per.3/12/97 morning meeting discussions)
--~--------DATES-------------------
luation *********
Correction ******
Sour 9e Record: 03/11/97
Eva Commitment:
Eval Due:
Corr Act Due:
Action Create: 03/24/97 Oria Eval Due:
. Orig CA Due:
Action Closed:
Eval Done:
Corr Act Done:
.__________ PEOPLE--------------------------------------
Respons4ble for Overall Action:
OPS Responsible for Current Pending Activity: OPS i
)
Issu9 Manager:
Init1ctor:
i Punchlist Administrator:
__________gpDATE--------------------------------
..____----REFERENCES----------------------------------------------------------
VARIOUS (SEE DESCRIPTION)

MISCELLANEOUS-------------------------------

XX Originating Agency:
System:
NRC Open Item Number:
NRC Status:
Related Outages:
Engineering Work Type: None Specified Person Hours:
Original EsQimate =
Current Estimate
=
Actual Hours
=
i
~
w 5,:
n y
l 1
l
' ACTION ITEM STATUS REPORT PAGE 1
03/26/97
co****************************
Responsible Person:
Urgency: NO DUE DATE ASSIGNED
Trkid: CR 7-0831 Work Priority: -100
'* Action Nu er:
2 ecocee*************************
Activity Pending is: RECEIVE ASSIGNMENT 1

TITLE AND TASK DESCRIPTION------------------------------------------

-Procedures Have Missing, Incorrect And/Or Inconsistent References To tcchnical Specifications Revicw the procedures listed under the Engineering section of the CR ent r rd description for adequacy of listing the ccrrect references.
a rev ons to procedures as necessary.
(per 3/12/97 morning meeting discuasions)
Sour a Record:-----DATES- /11/97 03
Evaluation ********* ****** Correction ******
(xmm tment:
Eval Due:
Corr Act Due:
Act:.on Create: 03/24/97 Orig Eval Due:
Orig CA Due:
Act:.on Closed:
Eval Done:
Corr Act Done:

PEOPLE-----------

Responsible for Overall Action:
?RE
' Responsible for Current Pending Activity: PRE Icsu Manager:
Init tor:
Punc ist Administrator:

UPDATE----------------------------------------------------

____..----REFERENCES----------------------------------------------------------
VARIOUS (SEE DESCRIPTION)

MISCELLANEOUS--------------

Originating Agency:
S stem:
XX NIO O en Item Number:
N C Status:
.Relat d Outaaes:
Engineering Work Type: None Specified Person Hours:
Original Es imate =
Current Est mate
=
Actual Hours
=
i q-
ACTION ITEM STATUS REPORT PAGE 1
03/26/97 Responsible Person: WILLIAM HEIN5NIN
Trk:.d: CR 97-0831 Urgency: NO DUE DATE ASSIGNED Work Priority: -100
Act:.on Nuder:
3 ecosee*************************
Activity Pending is: ACTION NEEDED

TITLE AND TASK DESCRIPTION------------------------------------------

Procedures Have Missing Incorrect And/Or Inconsistent References To technical Specifications, Review'the procedures listed under Maintenance ofthe description section of the parent CR record for adequacy of listin references, Make necessary procedure changes as necessary.g the correct (per 3/12/97 morning meeting discussions) i
_______... DATES----------------------- ----- --------------- Correction -
i Source Record: 03/11/97
Evaluation *********
+
Commitment:
Eval Due:
Corr Act Due:
Action Create: 03/24/97 Orig Eval Due:
Orig CA Due:
Action Closed:
Eval Done:
Corr Act Done:
PEOPLE--------------------------------------------------------------
1 Responsible for Overall Action:
MSV Responsible for Current Pending Activity: MSV Issue Manager:
Initiator:
1 Punchlist Administrator-1 I

UPDATE--------------------------------------------------------------

(03/25/97 Issued to Group: MSV
)
(03/25/97
) Received Action into Group: MSV l
Responsible Person:
j
.....-----REFERENCES------------------------------------------------------
VARIOUS (SEE DESCRIPTION)

MISCELLANEOUS----------------------

Originating Agency:
S stem:
XX NRC Open Item Number:
N C Status:
Related Qutages:
Engineering Work Type: None Specified Person Hours:
Original Estimate =
Current Estimate
=
Actual Hours
=
1 l
e= 4 m
ACTION ITEM STATUS REPORT-PAGE 1
03/26/97 oeoceoecoce********e***********
Responsible-Person:
-IN 31-60 UAYS Urgency: DUE
Trkid: CR 97-0831 Work Priority: -100
-
Action Number:
4 o*eeee*************************
Activity Pending is: ACTION NEEDED

TITLE AND TASK DESCRIPTION----------------------

Procedures Have Missing, Incorrect And/Or 'nconsistent Refererceo ~
technical Specifications Review the procedures..isted under the Health Physics area of the CR parent record descript:on section for adequacy in listing the correct references.
Make procedure changes as necessary.
(per 3/12/97 morning meeting discussions)
Sour e Record:-----DATES---- /97

ion ******

Evaluation *********
Correct 03/11 Comn tment:
Eval Due Corr Act Due: 05/09/97 Act:.on Create: 03/24/97 Orig Eva Due:
Orig CA Due:
05/09/97 Act:.on Closed:
Eval Done:
Corr Act Done:
___----PEOPLE--------------------------------------------------------------
- Responsible for Overall Action:
HP Responsible for Current Pending Activity: HP Issu9 Manager:
Initiator:
Punchlist Administrator:

UPDATE--------------------------------------------------------------

Responsible Person:
' ~ " - ~ '^
r,vnup: Hp (03/26/97 Received Action intn Due Date: 05/09/97
__________ REFERENCES--------------------------------------
VARIOUS (SEE DESCRIPTION)

MISCELLANEOUS--------------------

System:
XX Originating Agency:
NRC Open Item Number:
NRC Status:
Related Outages:
Engineering Work Type: None,Specified Person Hours:
Original Estimate =
Current Estimate
=
l Actual Hours
=
i t
L w%
a
_, y s
POINT BEACH UNIT 2 RESTART COMMITMENT INDEPENDENT REVIEW RESULTS Qggitment ID Number 7 Ce==i+=ent Description Complete a review of Unit 2 adnunistrative controls implementing or referencing Technical Specifications to ensure Technical Specification requirements are appropriately reflected in the admmistrative controls.
The scope of this review will be examining the identified documents for accuracy and compliance with requirements, j
per the criteria in the above paragraph. Should this review identify either generic issues or significant discrepancies which could negatively impact reactor saf'ety, the scope of the review will be expanded. Where discrepancies are.
-l identified, 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.
i Review Methodolorv l
ne Independent Review of Restart Commitment #7 was performed in conjunction with procedure reviews performed j
,,g' for the Independent Review of Restart Comndtment #8. Restart Commitment #8 conducted a review of representative Operations Technical Specifications Tests (TSs), inservice Tests (ITs) and Operations Refueling Tests (ORTS). Rese documents were also reviewed for appropriate references to the Technical Specifications. The documents include:
Technical SoecificationsTests Inservice Tests Ooerations Refueline Tests TS-10A, U2 - TS-72 IT-03 Ul IT-07 ORT-3 ORT-12 TS-3A, Ul TS-81 IT-06 U2 IT-10 ORT-6 ORT 15 TS-84 TS 34 U2 IT-09A U2 IT-ll ORT-ll ORT-66A IT-13 U2 IT-65 U2 ORT-33 ORT-80 IT-40 U1 IT-90 Ul ORT-68 Appendix G IT-215 U2 IT-335 U2 ORT-73 Appendix W IT-536 U2 IT-755 U2 IT-765 U2 IT-295A U2 Since the Technical Specifications Testing category primarily deals with satisfying the surveillances mandated by
,.,,, PPP Techt; cal Specificatione, Independent Review of this cptegory for Restyt Comm(tment #7.was expanded
' beyond the above listed TS surveillance procedures to include all TS tests (total 46).
a Page 1 of to r
A
3 POINT BEACH UNIT 2 RESTA'RT,_ COMMITMENT INDEPENDEN'l REVIEW RESULTS i
l Commitment ID Number 7 WE Licensing personnel prepared a database spreadsheet of PBNP Technical Specifications which are verified by procedures, checklists, and other applicable verifying documents. This database spreadsheet is contained in the NPL 97-0048 Memo from Dave Weaver to John Palmer, dated 2/28/97, titled " Evaluation of PBNP administrative Controls Implementation of technical Specifications".
Review Results The following is a listing of the procedures reviewed along with observations of the independent review.
Technical Soecifications Tests
1. TS 3 UI Main Turbine Stop and Govemor Valves with Turoine Trip Test (Quarterly)
TS 15.4.1.A (Table 15.4.1-1 Item 42', appropriately cited in procedure PURPOSE.
TS 15.4.1.B (Table 15.4.1-2 Item 18) appropriately cited in procedure PURPOSE.
2. TS-3A U1 Turbine Trip Test (Monthly)
TS 15.4.1.A (Table 15.4.1-1 Item 42) appropriately cited in procedure PURPOSE.
\\
3. TS-4 U2 Main Turbine Stop and Govemor Valves with Turbine Trip Test (Quarterly)
TS 15.4.1.A (Table 15.4.1-1 Item 42) appropriately cited in procedure PURPOSE.
TS 15.4.1.B (Table 15.4.1-2 Item 18) appropriately cited in procedure PURPOSE.
4. TS-4A U2 Turbine Trip Test (Monthly)
TS 15.4.1.A (Table 15.4.1-1 Item 42) appropriately cited in procedure PURPOSE.
5. TS-5 U1 Bi-Weekly Rod Exercise Test TS Table 15.4.1-2 Item 10 appropriately cited in procedure PURPOS'E.
6. TS-6 U2 Bi-Weekly Rod Exercise Test TS Table 15.4.1-2 Item 10 appropriately cited in procedure PURPOSE.
, s n,
i
7. TS-9 Control Room Heating and Ventilation System Monthly Checks Procedure PRECAUTIONS AND LIMITATIONS states that " Operation of this equipment is a Technical Specifications Requirement," yet does not sr afy which TS in the procedure PURPOSE.
Page 2 of 10 J
3 4
a-POINT BEACH UNIT 2 RESTART COMMITME.lT INDEPENDENT REVIEW RESULTS -
)
Commitment ID Number 7
8. TS 10 Local Leak Test of Containment Personnel Hatches j
i
- TS cited in procedure PURPOSE and PRECAUTIONS AND LIMITATIONS (2.2) do not match up to actual TS. TS Section 15.4.4 doesn't set forth leakage criteria - TS 15.3.6 does.
9. TS-10A Ul Contamment Airlock Door Seal Testing i
Procedure PURPOSE does not refer to Technical Specifications and should for consistency with other procedures.
j
'10. TS-10A Ul APP A Vacuum Pump Calibration i
i N/A
11. TS-10A Ul APP B Hatch Door Seals j
i N/A 12 TS-10A U2 Containment Airlock Door Seal Testing Unlike TS 10A Ul, TS-10A U2 procedure PURPOSE references TS 15.4.4. However, TS 15 3.6 should also V
be appropriately referenced.
13. TS-10A U2 APP A Vacuum Pump Calibration N/A
~
14. TS-10A U2 APP B Hatch Door Seals N/A
15. TS-30 U1 High and Low Head Safety Injection Check Valve Leakage Test (Cold Shutdown)
TS 15.3.16 and 15.4.16 appropriately cited in procedure PURPOSE.
16. TS 31 U2 High and Low Head Safety Injection Check Valve Leakage Test (Cold Shutdown)
TS 15.3.16 and 15.4.'16 appropriately cited in procedure PURPO,SE.
i i
17. TS-32 Safety Valve Position VeriScation - Subcooling Margin Computing System - Containment Purge Valve
)
o
(..
Position (Monthly) i
.N Table 15.4.1-1 Items 40 and 41 appropriately cited in procedure PURPOSE.
Table 15.4.1-2 Item 23 appropriately cited in procedure PURPOSE.
Page 3 of 10 i
J
1 v
~
POINT BEACH UNIT 2 RESTART COMMITMENT INDEPENDENT REVIEW RESULTS Commitment ID Number 7
18. TS 33 Ul SurveillanceTesting: Containment Accident Recirculation Fan-Cooler Units (Monthly) 1 TS 15.3.3.B.2.a,15.4.51.C.2, and ASME Section XI appropriately cited in procedure PURPOSE.
19. TS-34 U2 Surveillance Testing: Containment Accident Recirculation Fan-Cooler Units (Monthly) 4 TS 15.3.3.B.2.a,15.4.5.1.C.2, and ASME Section XI appropriately cited in procedure PURPOSE.
i
20. TS-35 UI Local Leak Test of Containment Purge Valves TS 15.4.4.11 does not now apply to testing of Containment Purge Valves.
21. TS-36 U2 Local Leak Test of Containment Purge Valves TS 15.4.4.I1 does not now apply to testing of Containment Purge Valves.
22. TS-37 U1 Containment Spray Nozzles Check (Frequency of Less than or Equal to Five Years) j TS 15.4.5.1.B.3 appropriately cited in procedure PURPOSE.
23. TS-38 U2 Containment Spray Nozzles Check (Frequency of Less than or Equal to Five Years)
TS 15.4.5.1.B.3 appropriately cited in procedure PURPOSE.
24. TS-39 Ul Main Steam isolation Valves Operability Trip Test TS 15.4.7 and ASME Section XI appropriately cited in procedure PURPOSE.
25. TS-40 U2 Main Steam Isolation Valves Operability Trip Test TS 15.4.7 and ASME Section XI appropnately cited in procedure PURPOSE.
26. TS-41 Ul Cross Over Steam Dump (Quarterly)
TS Table 15.4.1-2 Item 29 appropriately cited in procedure PURPOSE. TS 15.3.4.E should also be cited in the PURPOSE.
27. TS-42 U2 Cross Over Steam Dump (Quarterly) o TS Table 15.4.12 Item 29 appropriately cited in procedure PURPOSE. TS 15.3.4.E should also be cited in the A
PURPOSE.
Page 4 of 10 j
1 POINT BEACH UNIT 2 RESTART COMMITMENT INDEPENDENT REVIEW RESULTS
+
Commitment ID Number 7
28. TS-43 Pressurizer Heater Group Energy Input Test (Quarterly)
TS 15.3.1.A.6 and Table 15.4.1-2 Item 30 appropriately cited in procedure PURPOSE.
29. TS-44 Ul In-Place Testing of Main Steam Safety Valves - Refueling TS Table 15.4.1-2 Item 12 and ANSI /ASME OM-1-1981 appropriately cited in procedure PURPOSE.
30. TS-45 U2 In-Place Testing of Main Steam Safety Valves - Refueling ANSI /ASME OM-1-1981 appropriately cited in procedure PURPOSE. TS Table 15.4.1-2 Item 12 should also be cited in procedure PURPOSE.
31. TS-70 Monthly Diesel Engine-Driven Fire Pump Functional Test TS 15.3.14 should be cited in addition to TS 15.4.15 in the procedure PURPOSE.
32. TS-71 Monthly Electric Motor Driven Fire Pump Functional Test TS 15.3.14 should be cited in addition to TS 15.4.15 in the procedure PURPOSE.
33. TS-72 Annual Fire Pump Capacity Test TS 15.3.14 should be cited in addition to TS 15.4.15 in the pre:edure PURPOSE.
34. TS-73 Monthly Fire Protection Control Valve Position Verification TS 15.3.14 should be cited in addition to TS 15.4.15 in the procedure PURPOSE.
35. TS-74 Annual Underground Fire Main Flow Test TS 15.3.14 should be cited in addition to TS 15.4.15 in the procedure PURPOSE.
36. TS-75 Biennial Service Testing of Fire Hose and Fire Hose Stations TS 15.3.14 should be cited in addition to TS 15.4.15 in the procedure PURPOSE.
>a w
m
37. TS-76 Quarterly Automatic Sprinkler and Water Spray System Surveillance Test TS 15.3.14 should be cited in addition to TS 15.4.15 in the procedure PURPOSE.
38. TS-77 S:mi-Annual Smoke Detection System.ntegrity Test Page 5 of 10
]
POINT BEACH UNIT 2 RESTART COMMITMENT INDEPENDENT REVIEW RESULTS Commitment ID Number 7 TS 15.3.14 should be cited in addition to TS 15.4.15 in the procedure PURPOSE.
39. TS-77 APP A Non-Technical Specification Related Smoke Detector N/A
40. TS-78 Semiannual Halon 1301 Fire,Supression System Surveillance Test TS 15.3.14 should be cited in addition to TS 15.4.15 in the procedure PURPOSE.
41. TS-79 Monthly Surveillance of Fire Hose Stations TS 15.3.14 should be cited in addition to TS 15.4.15 in Ae procedure PURPOSE.
42. TS-80 Sampling of Emergency Fuel Oil Tank (T-72), Fuel Oil Storage Tanks (T-175 A,B) and EDG Day Tanks (T-31A,B & T 176A,B)(Quarterly)
TS 15.3.14 should be cited in addition to TS 15.4.15 in the procedure PURPOSE.
}
TS 15.4.6 appropriately cited in the PURPOSE.
i
43. TS-81 Emergency Diesel Generator G-01 (Monthly)
TS 15.4.6.A.1,15.4.6.A.5 and ASME Section XI appropriately cited in procedure PURPOSE.
j
44. TS-82 Emergency Diesel Generator G-02 Monthly I
TS 15.4.6.A.1,15.4.6.A.5 and ASME Section XI appropnately cited in procedure PURPOSE.
45. TS 83 Emergency Diesel Generator G-04 Monthly e
TS 15.4.6.A.1,15.4.6.A.$ and ASME Section XI appropriately cited in procedure PURPOSE.
46. TS-84 Emergency Diesel Generator G-04 Monthly j
T(15.4.6.A.1,15.4.6.A.5 and ASME Section XI appropriately cited in procedure PURPOSE.
1 Inservice Tests
1. IT-03 UI Low Head Safety injection Pumps and Valves (Quarterly)
TS 15.4.5.II.A.1 and ASME Section XI appropriately cited in procedure PURPOSE.
Page 6 of 10
1
.L POINT BEACH UNIT 2 RESTART COMMITMENT INDEPENDENT REVIEW RESULTS Commitment'ID Number 7
2. IT-06 U2 Contamment Spray Pumps and Valves (Quanerly)
TS 15.4.5.II.A.1 appropriately cited in procedure PURPOSE.
3. IT-07 Service Water Pt.mps and Valves (Quarterly)
ASME Section XI appropiiately cited'in procedure PURPOSE.
4< IT-09A U2 Cold Start Testing of Turbine-Driven Auxiliary Feed Pump and Valve Test (Quarterly)
TS 15.4.8.1.b,15.4.8.1.c, Table 15.4.1-1 Item 20, and ASME Section XI appropriately cited in procedure
-PURPOSE.
5. IT-10 Test of Electrically-Driven Auxiliary Feed Pumps and Valves (Quarterly)
TS 15.4.8.1.a.15.4.8.1.c, and ASME Section XI appropriately cited in procedure PURPOSE.
Table 15.4.1-1 Item 20 should also be cited in the PURPOSE.
i
6. IT-11 Spent Fuel Pool Cooling Pumps (Quarterly)
ASME Section XI appropriately cited in procedure PURPOSE.
. 7. IT-13 U2 Compcnent Cooling Water Pumps and Valves (Quanerly)
ASME Section XI appropriately cited in procedure PURPOSE.
8. IT-40 Ul Safety injection Valves (Quarterly)
ASME Section XI appropriately cited in procedure PURPOSE
9. IT-65 U2 Containment Isolation Valves (Quanerly)
ASME Section XI appropriately cited in procedure PURPOSE.
-10. IT-90 Ul Atmospheric Steam Dump Valves (Quarterly) 5 ASME Section XI and TS Table 15.4.1-2 Item 28 appropriately cited in procedure PURPOSE.
11. IT-215 U2 Safety injection Valves (Quanerly) i ASME Section XI appropriately cited in procedare PURPOSE.
A Page 7 of 10
^'
+
POINT BEACH UNIT 2 RESTART COMMITMENT INDEPENDENT REVIEW RESULTS 4
Commitment ID Number 7)-
n 12., IT 295A U2 Auxiliary Feedwater System Flow Paths'and Indier. ors TS Table 15.4.1-1 Iteni 20 appropriately cited in procedure PU70SE.'
13. IT-335 U2 Contamment Isolation Valves (Cold Shutdown)
ASME Section XI appropriately cited in procedure PURPOSE.
14. IT-536 U2 _ Containment Sump B Suction Line Leak Test (Refueling Shutdown) f ASME Section XI and TS Table 15.4.1-2 Item 22 appropriately cited in procedure PURPOSE.
Procedure refers to TS 15.4.4.IV.A.I.b. There is no such TS.
15. IT-755 U2 Flow Test of Low Head Safety injection Check Valves (Refueling)
.TS 15.3.1..A.3.b appropriately cited in procedure PURPOSE.
' 16. IT-765 U2 Flow Test of High Head Safety Injection Check Valves (Refueling) l ASME Section XI appropriately cited in procedure PURPOSE.
,Onerations Refuelina Tats 1
1. ORT-6 Contair:nent Spray Sequence Test Unit 2 TS 15.4.5.: 31 and 2 appropriately cited in procedure PURPOSE.
2. Appendix G Nitrogen to SI Accumulators N/A
3. Appendix W Spray System, B Train, Contaimnent Isolation Valves N/A
4. ORT l! CVCS and CC Systems Check Valve Stroke. L t ASME Section XI appropriately cited in procedure PURPOSE.
. o 15. ORT 12 Fuel Transfer Tube Flange Seal Technical Specifications are referred to generally in the procedure PURPOSE. Procedure should state specific
'k applicable Technical Specifications in procedure PURPOSE.
Page 8 cf10
-N
..~
y, i
. POINT BE'ACH UNIT 2 RESTART COMMITMENT
./
INDEPENDENT REVIEW RESULTS -
fdmmitment ID Number 7 f 6.. ORT-15 Fuel Manipulator and Fuel Transfer System Ch'eckout TS Table 15.4.1-2 Item 14 appropriately cited in procedure PURPOSE..
7f ORT-33' Post Accident Containment Ventilation System FASME Section XI appropriately cited in procedure PURPOSE.
PURPOSE does not state which TS specifies the applicable Appendix J requirements.
8. ORT-66A Containment Pressure (P31A).
v Procedure PURPOSE does not specify TS or Appendix J requirements for leak test.
9. ORT-68 Component Cooling Water to and from 2P-I A - Refueling Shutdown Procedure PURPOSE should cite TS 15.3.6.A.I.b in addition to Appendix J.
10. ORT-73 ' Electrical Penetration Leak Test Procedure PURPOSE should cite TS section for Appendix J Type B testing.
I1. ORT-78 Mechanical Penetration LeakTest Procedure PURPOSE snould cite TS section for Appendix J Type B testing.
12. ORT-80 Mechanical Penetration Leak Test (P29,13,27)
Procedure PURPOSE should cite TS section for Appendix J Type B testing.
An Independent Review confirmed that the WEPCO " Evaluation of PBNP Administrative Controls Implementation of Techt.al Specifications" distributed in Memo NPL 97-0048 satisfies the Restan Commitment to perform this review. It is noted however, that the WEPCO review identified potential Technical Specification violations; identified numerous procedural deficiencies and makes a recommendation for a more thorough review of the implementing procedures for technical accuracy. From discussions with the responsible person, these identified
}$ sues are to be captured within the Condition Reporting Process and tracked to resolution.
v.
w; -
~,
l
^ ' '
\\
Page 9 of10 c.
s_
POINT BEACH UNIT 2 RESTART COMMITMENT INDEPENDENT REVIEW RESULTS Commitment ID Number 7 Recommendations.
Make revisions as appropriate tv address the above observations. Incorporation should be tracked to schedule the Ecessary procedure revisions to be accomplished prior to next scheduled performarre of the procedure. Some minor items may, however, be deferred until the next scheduled procedure review commensuate with their safety significance. Some of the observations discussed above may be common to other procedures which were not reviewed as part of this Independent Review. It is recommended that the necessary procedure changes be made as part of the system review of procedures which is recommended by the Independent Review of Startup Commitment i
8. These discrepancies as well as those identified by the WEPCO review appear to be symptoms of a condition that will require additional review for root cause determination. This suggested root cause review is considered a long term programmatic enhancement and not a restart prerequisite The benefits of maintaining a database which cross-references Technical Specifications with the applicable documents that verify the Technir ! Specifications is obvious. As a basis document, whenever Technical Specifications are changed, tne affected docaments (i.e., procedures, checklists, etc.) need to be tracked for necessary changes.
. Based en the Independent Review, there are no items involved with Commitment #7 which would impede Unit 2 startup.
'o o
Reviewed By:,
(
Q N-Page 10 of 10
3 ACTION ITEM STATUS REPORT PAGE 1
03/31/97 Responsible Person:
c' Trkid: U2R22 RESTART Urgency: vums Work Priority:
99
Action Number: 15 Activity Pending is: DONE ASSOCIATED WITH A COMMITMENT

TITLE AND TASK DESCRIPTION---- --- ---------------------------------

Unit 2 Refueling 22 Startup Commitments review 20% of the maintenance work orders Prior to leaving cold shutdown $ on Unit 2 or Common PSA safety significant performed since January 1, 199 systems (AFW, SW, EDG IA 4.16 kv, gas turbine and CCW) to verify adequate PMT was perfo,rmed to ensure system / comp,onent safety function.
i
....------DATES--------------------
luation *********
Correction ** ***
Source Record: 01/10/97
Eva Commitment:
Eval Due:
Corr Act Due: 03 21 97
)
Action Create: 01/13/97 Orig Eval Due:
Orig CA Due:
02 11 97 Action Closed: 03/31/97 Eval Done:
Corr Act Done:03 19 97 PEOPLE--------------------------------------------------------------
j
- ~ ~ "
Responsible for Overall Action:
MSV Responsible for Current Pending Activity:
Issue Manager:
.u Initiator:
Punchlist Administrator:
.....-..--UPDATE---
(01
) QA has been graicous enough to take the lead on this effo/15/9' has charted a team to perform these reviews. The team is rt..
currently in the process of reviewing WO's from history.
Changed Responsible Group:ponsible Person:
(01/15/97
. Changed Res From to From (.MT) To (MSV)..
(01/20/97 Changed Responsible Person: From
) to l
(01/30/97 Set Work Priority to 29.
Changed the Due Date from:
02 to 02/28/97 scheduled to leave cold shutdown in early/11/97 (02/10/97 March
~
Unit (02/11/97 The 20% screening has been completed. Determinations are being made if additional evaluations are needed.
(02/26/97 Changed the Due Date from:
02/28/97 to 03/21/97 outage delays.have pushed heat up to the end of march.
(03 Passed to for Verification.
The/19/97 review has been completed by QAS. The surveillance report has been documented in the Quality Assurance Program Surveillance Report #
S-P-97-01.
(03/28/97 Passed to 7
___a for Final Close Out.
Reviewed the documentation.
This item is ready for closecut.
(03/31/97.
PLA Closure of Item.
OA Surveillance Report S-P-97-01 dated March 12, 1997 was performed January 20-February 10, 1997.
s s
-REFERENCES--------------
S-P-97-01 QCR 97-0002 CR 97-0005 QCR 97-0006 CR 97-0007 QCR 97-0008 CR 97-0009 QCR 97-0010 CR 97-0011 QCR 97-0012 CR 97-0013

...--MISCELLANEOUS----------------------

Originating Agency:
S stem:
XX NRC Open Item Number:
N C Status:
Related Outagen:
U2R22 Engineering work Type: None Specified 1
Persor. Hours:
Original Estimate e.
e

NPL-97-0127, Forwards Documentation for Review by NRC to Support Restart Issues as Identified on Unit 2 Startup Commitment List.Items Are Listed

Contents

Text

.

REFERENCES:

REFERENCES:

REFERENCES:

REFERENCES:

REFERENCES:

REFERENCES:

REFERENCES:

REFERENCES:

Navigation menu

NPL-97-0127, Forwards Documentation for Review by NRC to Support Restart Issues as Identified on Unit 2 Startup Commitment List.Items Are Listed

Text

.

REFERENCES:

REFERENCES:

REFERENCES:

REFERENCES:

REFERENCES:

REFERENCES:

REFERENCES:

REFERENCES:

Navigation menu

Search