ML20084R758

Conformance to NRR Generic Ltr 82-16,JM Farley Nuclear Plant,Units 1 & 2

ML20084R758
Person / Time
Site:	Farley
Issue date:	10/31/1983
From:	Beahm D EG&G, INC.
To:	NRC
Shared Package
ML20084R743	List: ML20084R758
References
CON-FIN-A-6600, RTR-NUREG-0737, RTR-NUREG-737, TASK-1.A.1.1, TASK-1.A.1.3, TASK-2.E.1.1, TASK-2.E.1.2, TASK-2.E.4.1, TASK-2.E.4.2, TASK-2.K.2.08, TASK-2.K.2.10, TASK-2.K.2.13, TASK-2.K.3.03, TASK-2.K.3.12, TASK-TM EGG-EA-6431, GL-82-16, NUDOCS 8405230150
Download: ML20084R758 (9)

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D EGG-EA-6431 CCNFORMANCE TO NRR GENERIC LETTER 52-16 JOSEPH M. FARLEY NUCLEAR PLANT UNITS 1 AND 2 David M. Beahm Published October 1933 EG&G Idaho, Inc.

Icabo Falls, Idaho 83415 Prepared for the -

U.S. Nuclear Regulatory Commission Atlanta, Georgia 30303 Under COE Contract No. CE-AC07-76IC01570 FIN No. A6600 l

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This EG&G Icaho, Inc., re: ort: evaluates the submittal proviced by i 2 Alabama Power Comoany (APCo) for Farley Nuclear Plants Unit Nos.1 and 2.

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The submittal is in response to , Generic Letter No. 32-16, NUREG-0737 Technical Specifications. Acplicaole sections of the plants' technical specifications are evaluated to determine ccmpliance to the guideline's-estaclished in the generic letted

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This report is supplied as part of the " Technical Assistance for Operating Reactors Licensing Actions," being conducted for the U.S.' Nuclear

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Regulatory Commission, Region II, by EG&G Idaho, Inc., NRC Licensing Support Section.

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[ The U.S. Nuclear Regulatory Commission funded the work under. ,

i I authorization B&R 92-19-20-10, FIN No. A6600.

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Docket Nos. 50-348 and-50-364

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o. -TAC Nos. 49731 and ?9732 A

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1. INTRODUCTION . . . .. . . . .. . .. . 1

2. REVIEW REQUIREMENTS . . .. .. . . 2 2.1 STA Training (I . A.1.1.3) . .. . . . 2 2.2 Sni f t Manning-Overtime Limits (I. A.1. 3.1) . . .. 2 2.3 Short Term Auxiliary Feecwater System ( AFWS) Evaluation (II.E.1.1) . . . .. . .. .... . . ... .. . 3 2.4 Safety Grade AFW Initiation anc Ficw Indication (II .E.1.2) . ... .. . .. . . ...... . ... .. 3 2.5 Dedicatec Hydrogen Penetrations (II.E.4.1) .. . ... . 3

2.6 Containmen

Pressure Se:ccin (II.E.4.2.5) . ... ..... 3 2.7 Containmen Purge Valves (II.E.4.2.6) .. ... . ....... 4 2.8 Radiation Signal on Purge Valves (!I .E.4.2.7) . . . . . . . . . . . . A 2.9 Upgrace Babcock and Wilcox (B&W) AFWS (II.K.2.3) . . a 2.10 B&W Safet'-Grade y Anticipatory Reactor Trip (II.K.2.10) . . 5 2.11 B&W Thermal-Mechanical Report (II.K.2.13) .. . ..... 5 2.12 Recor:ing Safety and Relief Valve Failures and Challenges (!!.K.3.3) . . .. .. . .. .. . . . .. . . 5 2.13 Anticipatory Trip on Turbine Trip (II.K.3.12) . . . . .. . 5

3. EVALUATION ........ .. ..... .. ......... ........ .... . .... . 7 3.1 STA Training (I.A.I.1.3) . . ..... . .. ......... .. .. 7 3.2 Shi f t Manni ng--Overtime Limi ts (I . A.1.3.1) . . . . . . .... . 7 3.3 Short Term Auxiliary Feecwater System (AFWS) Evaluation

(!I.E.1.1) .... . .... ................. ....... .. . 3 3.4 Safety Grade AFW Initiation and Flow Indication ,

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( II . E.1. 2 ) . . . . . . . . .. .. ............. . .......... . 3, 3.5 Dedicated Hydrogen Penetrations (II.E.4.1) . . . . ... . .. 3 111 L_ .

3.5 'ontainmen- Pressure Se: point (II.E.J.2.5) 3 3.7 Containment Purge Valves (II.E.4.2.5) . .. .. 9 a.e Raci a t' on s i gna i on ru rge ',,a i ve s ( 11.: .. . , . , . ,/ ) . . e.

3.9 Uograce Babcock an: Wilcox (E&W) AFWS (II.K.2.5) 9 3.10 S&W Safety-Grade Anticicatory Reae:ce Trip (II.K.2.10) 9 3.11 2&W Inermal-vecnanical Recort (II.K.2.13) .. . 10 3.12 Reporting Safety and Relief Valve .ailures and Challenges (II.K.3.3) . .. .. .. . .. . 10 a.la, 3.nticipatory .rio on .t u rc i n e i r l p ( ., , 1. .< . .a.,,) . ,0 4 CONCLUSICNS . . . . .. . . ..... . 11

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r CCNFORMANCE TO NRR GENERIC LETTER 32-16

'OSEPH M. FARLEY NUCLEAR PLANT UNITS 1 AND 2 I

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1. INTRCDUCTION On Sectemoer 20, 1982, Generic Letter 32-161 was. issued by D. G. Eisenhut, Director of Licensing, Office of Nuclear Reactor RegulaLion (NRR), to all pre'ssurized power reactor licensees. This letter identified 2

a number of items recuired by -NUREG-0737 to be implemented in the licensee's Technical Specifications (TS) by December 3, 1981. Each licensee was' requested to review their. facility's TS, to adcress areas of compliance, and to identify deviations or absence of a specification for the items identified in the generic letter within 90 days of receipt of the letter.

The Alabama Power Company (APCo), the licensee for Farley Nuclear Plant Units 1 and 2, provided a response to the generic letter on Novemoer 19, 1982.3 This submittal states that Farley' Nuclear Plant Units 1 and 2 meet the recuirements of Generic-Letter 32-16 and no, tecnnical scecification changes are required.

This interim report provides an. evaluation of the . licensees lTS4 '

and the Nuclear Regulatory Commission's (NRC) correspondence with the licensee' pertaining to those items identified _in the generic letter.

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'2. REVIEW RECUIRE. VENTS The review consists of evaluating the licensee's response, currently approvec TS,.and etner NRR apcrevals against the criteria set fortn in Generic Letter 32-16. Ine NUREG-0737 items and the criteria established are as folicws:

2.1 STA Trairine (I.A.1.1.3)

The licensee is to accress within their TS that a shift technical advisor (STA) to the shift supervisor is creviced. In acdition, the qualifications, training, and on-duty reauirements for the STA should be stated.

2.2 Shift Marninc-Overtime Limits (I. A.I.2.1)

The licensee is to previce cnanges to tneir T3 providing overtime acministrative crececure and staffing requirements. The following guicelines were established for the licensee by the NRC.

"a. An indivicual snculc not be cermitted to work more than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> straignt (excluding shift turnover time).

b. An indivicual should not be permitted to work more than 16 nours in any 24-hour pericc, nor more tnan 2d hours in any a8-hour serioc, nor more nan 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in any seven cay pericc (all excluding shift turnover time).

c. A break cf at least eight hours should be allowed between work periods (inclucing shift turnover time).

d. Except curing extended shutdown periods, the use of evertime should be consicered on an-indivicual basis and not for the entire staff on a snift.

Recogni:ing that very unusual circumstances may arise recuiring deviation from the above guicelines, such ceviation snall be authorized by One plant manager cr his ceputy, or higher levels of management. The

. paramount consiceration in sucn authorization shall Oe tnat significant recuctions in the effectiveness of c;erating personnel would be hignly uniikely.

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• In acci:for. :rececures are encourage: tha: wculo allow licensec ccera: Ors a: :ne con:rcis := ce cericcicai!y relievec anc assicnec :o :ce-cuties away fr0m tne control boarc curing neir tour of cu:y."4 2.3 Snort Term Auxiliary :eecwater System (AFWS) Evaluation (II.E.'. 1) are cojective ci :nis item is to incrove the reliacility and cerformance of the auxiliary feecwater (s,ed) system.

-isdecenc on :ne results of tre licensee's evaluation arc :ne staff review, and are ceing cevele:ec se:arately for each plant. The limiting concisions of oceration (LCO's) and surveillance recuirements for :ne AFW system snoulc be similar T

to c:ner safety-related systems.'

2.4 Safety Grade AFW Initiation and Flcw Indication (II.E.1.2)

The AFW system automatic initia:icn system was to have Deen control grade by June 1.1980, anc safety grace ey July 1,1981; the AFW system flow incication was to have been control grade by January 1,1980, anc 1

safety grade by July 1, 1951.-

2.5 Decicated Hycrocen Penetrations (II.E.4.1)

Flants that use external recocciners er purge systems for cos:-accicen: cccoustible gas control of the containment atmosphere sncuic provide containment penetrations cedicated to that service. In satisfying-this item, scme clants may nave to acd seme accitional piping and valves.

If se, these valves should be subjected to the requirements of Apcencix J of 10CFR 50, anc the T5 snould ce mecif.ied acc:rdingly.1 '

2.6 ventainmen

res sure Set:cint ( 1:.:.. .a.2. _)

0 The containmen; cressure setcoint :nat initiates containmen; isolation must be reduced : the minimum ccmpatible witn ncemal coerating conditions. Most plants provided justification for. not changing tneir-se: point and the NRC nas approvec tneir justification Oy secarate

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correspencence. The remaining plants must submit a cnange :: the-75 witn t

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tne lower containment pressure setocint and orovice justification if tnis

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setpoint is more than 1 psi above maximum expected containment pressure during normal-operation 1 .

2.7 Containment purpe Valves (II.E.4.2.5)

Model TS were sent separately to each plant as part of the overall

- containment purge review. .These TS'. include the requirement that the containment purge valves be locked closed except for safety related activities, verified' closed at least every 31 days, and be subjected to leakage rate limits.I 2.8 Radiation Sicnal on Purge Valves (II.E.4.2.7)-

The containment purge valves must close promptly to reduce:the amount of radiation released outside containment.following a release of radioactive materials to containment. TS should include the requirement that at least 'one radiation monitor that automatically closes the purge

. valves uoan sensing'high radiation in theLeontainment atmosphere be .

operable at all times except cold shutdowns and refueling outages. If not .

operable, either the plant should begin proceeding to colc shutdown'wi. thin 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or tne. purge valves shoul.d be closed within.24Ehours. Model TS were orovided in Standard Technical Specifications; format, for' thosej ciants

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that are using safety grade ccmponents to satisfy tne;recuirement.

2.9 . Uograde Babcock and ~Wilcox (2&W) AF4S' (II.K.2.3)

Additional;long-term APWS modifications were to be performed;in .

. conj ucti on with- Generic, Letter 82-161-Items 3.a'nd V(~ items. 2.3- and 2.41 x

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, above). The1TS imolemented for.' Items- 3 ?and -4. will. 'ai so _ address- .the Tupgrace .

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. of.the'S&W AFdS; therefore no separate TS would be1 required for:this item for:.the .S&W Plants;

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2.10 B&W Safety-Grace Anticioatory Reactor Trio (II.K.2.10)

Safety grace turoine trip-equipment initiating a reactor trip was to

.be. implemented by tne.B&W designed plants as part of tne TMI iessons learned. The licensee is to imolement in the TS the trip setpoint, numcer of cnannels, tric conditiens, minimal channels recuired for oceration, applicable operating : odes, actions to be taken, surveillance required anc any other requirements for safety grade equipment, 2.11 B&W Thermal-Mechanical Recort (II.K.2.13)

Licensees of E&W operating reactors were required to submit by January 1, 1981, an analy' sis of the thermal-mechanical conditions in the reactor vessel during recovery from small breaks with an extended loss of all feeawater. TS, if required, will be determined following NRC staff review.1 .

2.12 Recortina Safety and Relie'f Valve-Failures and '

Challences (II.K.3.3)

-NUREG-0660 stated that safety and relief valve failures be recortec promptly and challenges be reported annually. The sections of the TS that-discuss. reporting requirements should be accordingly~. changed. The NRC has noted that an acceptable alternativefwould be to report challenges

. monthly.1 2.13 Anticicatory-Trio on Turbine Trio (II.K.3.12)

Licensees' with Westinghouse-cesigned operating plants have confirmed that their plants have an anticipatory reactor trip' upon turoine trip'.

Many of these plants'already have'tnis. trip in the TS. For-those that do-not, tne_ anticipatory tric shoulc be added tolthe TS.

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For the Farley Nuclear Plants Units Nos. 1 anc 2, the above :. ems 2.9, 2.10, anc 2.11 are not being evaluated. Seing a Westinghouse cesign

tems 2.9, and 2.10 are not applicable for Farley Nuclear Plants Uni:

Nos. 1 and 2. For item 2.11, the thermal-mechanical report is being evaluated oy :ne NRC staff as an active Three Mile Island (TMI) action item uncer TAC number 46536 snd 15237.

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3. EVALUATION The evaluations of Generic Letter 32-16 Items 1, 2, 3, t, 5, 6, 7, 5, 12 and 13 are as follows:

3.1 STA Traininc (I.A.1.1.3)

The licensee's resconse statec that tnis item is addressed in the original Unit 2 TS anc Amencment No. 25 to the Unit 1 TS. Section 6.2.4 of a

the TS# '* establishes the STA position and advisory capacity; however, no cetailed information is orovided on STA training within the TS.

Section 6.4 of the TS provides tnat a retraining and replacement training program for the facility staff be maintained under the direction of the C Training Sucerintendent which meets or exceeds the requirements and recommendations of Section 5.5 of ANSI NIS.1-1971, Appendix A of 10 CFR-Part 55 anc the supplemental requirements specified in the March 2S, 1930, NRC letter to all licensees.

Consistent witn :ne guicance crovided in the Generic Letter 82-16, no licensing action is requirec until furtner guicance is issued by the Ccemission.

3.2 Shi f t Manninc--Overtime Limi ts (I . A.1.3.1)

The existing Farley TS"'6 co not accress this item. The licensee nas sucmitted an applicati.cn, datec June 6, 19837 , to amend the Unit 1 anc 2 TS. The amendment will add page 6-la to the existing TS concerning acministrative procedures to limit the working hours of unit staff who

_ perform safety-related functions. The amencment folicws the guidelines recommended in Generic Letter S2-16. The accectance and incorporation of the amendment will satisfy tne NUREG-0737 recuirements. This item is also being handled by the NRC staff under.an active TMI action' item, TAC numcer 44088 and d4089.

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3.3 Srcr: Te- Auxiliary :eecuater System Evaluaticn (II.E.1.1) -

Q In a review of Amencment No. 25 to Carley Uni: 1~ TS, tne NRC previced a safety evaluation statement of tre Auxiliary Feecwater System (AFWS) for Units 1 and 2. As incicated in the safety evaluation, AFW issues rave been resclved arc are acceptacle. 75 Section 3.7.1.2 anc 4.7.1.2 are acclicaole for :arley Units 1 and 2 and meet tne recuirements of Generic Letter 32-15. No further licensing action is necessary.

a.3 ,. a r. e y a rac e n, ,a, sy s t em i n 4. . i a t i e n a nd r-,i o.. i n e ,. c a t i o n ( 11.:

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The licensee's response stated that the requirements were addressed in the original Uni 2 75 and Amendment No. 25 tc the Unit 1 TS. As stated in Section 3.3 above, the AFW issues nave been resolvec and are acceptable. A review of the licensee TS for Units 1 and 2 shows :nat the AFW Initiation and Flow Incica:fons items are acdressed in Tables 3.3-11, 4.3-7, 3.3-3, 3.3-4, 3.3-5 anc 4.3-2. This meets the criteria set forth in Generic Letter S2-15. No fur ner licensing action is necessary.

3.5 Cedicated 'Hycrecen Oenetrations (II.E.a.1)

Tne hydrt. gen recombiners at the Farley Nuclear Plant are internal te ne ccntainment builcing, thus tne requirements of NUREG-0737 Item II.E.a.1 are not apolicaole. No licensing action is necessary.

3.5 Centainment :-essure Setcoint (II.E.a.2.5)

The licensee's rescanse statec that the recuirements were acdressed in the original Ur;it 2 TS anc Amencment No. 25 to the Unit 1 TS. A review of the licensee's TS verifiac the containment pressure setcoint of a psig has been incor; crated into Tacle 3.3-a. This item nas ceen founc accepta 1e by the NRC as indicated in a letter to Alabama ?cwer Co., datec Augus 5, c

1981.' No further licensing ac:f on is necessary for this item

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3.7 : Containment Purge Valve (II.E.4.2.6)

The licensee's response stated that the requirements were adcressed in tne original Unit 2 TS and Amendment No. 26 to the Unit 1 TS. A review of the licensee TS shows this item is adcressec in Sections 3/4.3.2, 3/4.6.1.1, 3/4.6.4.l.7, and 3/4.9.9. This item has been found acceptable to the Generic Letter 32-16 requirements for both units, as indicatec by NRC safety evaltation of Amencment No. 26 to Farley Unit 1, catec March 1, 1932.

No further licensing action is necessary.

3.3 Radiation Signal on Purge Valves (II.E.4.2.7)

The licensee stated that this item is addressed in the origina', Unit I anc Unit 2 T3. Our review of the current TS indicates this item is~in Sections 3/4.3.2, 3/4.3.3 and 3/a.9.9 and verifies purge anc exnaust isolation valves are actuated by containment radiation monitoring instrumentation. No furtner licensing action is necessary.

3.9 Ucgrace Baccock and Wilcox (B&W) AFWS (II.K.2.3)

Farley Units 1 and 2 are a Westinghouse design and, therefore, the requirements of this item are not applicable. No licensing action is required.

3.10 S&W Safety-Grade Anticicatory Reactor Trio (II.K.2.10)

Farley Units 1 and 2 are a Westinghouse design and, therefore, the -

requirements of tnis item are not applicable. The anticipatory trip is evaluated uncer NUREG-0737 Item II.K.3.3 for tne Westingnouse design. No.

licensing action is required.

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3.11 S&W Thermal-Vechanical Recort (II.K.2.13)

Farley Units 1 and 2 are a Westingnouse cesign and, tnerefore, the requirements of nis item are not applicable. It has been noted that there is an active TMI action item Thermal-Mechanical Report for Units 1 anc -2 under TAC Numcers 16SS6 and 46337. No licensing action is required cy Generic Letter 52-16 for snis item.

3.12 Recortino Safety Valve and Relief Valve ra ilures and Challences (II.X.3.3)

The licensee statec that tne requirements were ac.ressec in Amencment No. 26 to tne Unit i TS and in the original Unit 2 TS. Our review of tne TS incicites tne Generic Letter 32-16 requirements are met by Sections 6.9.10 and 6.9.1.12. The NRC nas found tnis item acceptable as indicated in a letter, O dated March 26,'1982, to the utility. No further licensing action is necessary.

3.13 Anticioatory Trio on Turbine Trio (II.K.3.12)

The licensee's resconse statec that this item is accressed in tne original Unit 1 and Unit 2 TS. Cur review of the TS verifies the anticipatory reactor trip, upon turcine trip, is acdressed in TS Sections 2.2 anc 3/4.3.1. The flRC nas founc this item acceptable as indicated by a letter,I datec January 6,1982, to the utility. No further licensing action is necessary.

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c.. . _ _ . - _____ - ___ _________ _ ____ _ _ _ _ _ __ - _ _ _ _ -

.4 CONCLUSICNS Based on our review, we find the licensee conforms to those issues accressed in Generic Letter 32-16 on TS with the exceation of these icentified in Section 3.1, STA Training (I. A.1.1.3), which requires furtner NRC guidance, and Section 3.2, Shif t Manning-Overtime Limits (I.A.1.3.1),

which requires acceptance and incorporation' of a proposed TS amendment requested by the licensee.

11

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5. REFERENCES

1. O. G. Eisenhut, NRC letter to all 3ressuri:ed Reactor Licensees, "NUREG-0737 Tecnnical Soecifications (Generic Letter 32-16),"

September 20, 1932.

2. NUREG-0737, Clarification of TMI Action Plan Recuirements, oublisned by the Division of Licensing, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Ccmmission, Novemoer 1930.

3. F. L. Clayton, Alabama Power Comoany letter to S. A. Varga, Nuclear Reactor Regulation, "Joseon M. Farley Nuclear Plan: Units 1 and 2 NUREG-0737 Tecnnical Specifications (Generic Letter 32-16),"

j Novemcer 19, 1932.

4. O. G. Eisennut, NRC letter to All Licensees of Operating Diants,  ;

Acolicants for an Ocerating License, and Holcers of Construction Permits, " Nuclear Power Diant Staff Working Hours (Generic Letter No. 32-12)," June 15, 1932.

i

5. Farley Nuclear Plant Unit 1 Technical Specifications, Apcendix A to License No. NPF-2, Amencment No, 26, March 1,1982.

6. Farley Nuclear Plant Unit 2 Technical Specifications, Acpendix A to License No. NPF-E, Amendment No. 13.

J

7. F. L. Clayton, Alacama Power Comoany letter to S. A. Varga, Nuclear Reactor Regulation, "Joseon M. Farley Nuclear Plant Units 1 and 2 Facility Staff Tecnnical Soecification Change Request NUREG-0737, Item I.A.I.3 Generic Letter Nos. 32-C2 and 82-12," June 6, 1953.

4

8. Edward A. Reeves, NRC letter to F. L. Clayton, Alabama Power Ccmpany,

" Transmittal of Amencment No. 26 to Farley Unit No I with Safety Evaluation and Environmental Protection Plan related to Amancment 25,"

l Maren 1, 1982.

4 9. S. A. Varga, NRC letter to F. L. Clayton, Alabama Power Comcany, "Comoletion of Generic Item B-24 and TMI Action Item II.E.4.2.5,"

August 5, 1981.

i,

10. S. A. Varga, NRC letter to F. L. Clayton, Alacama Power Company, "TMI Action Plan Item II.K.3.3, Reporting Relief Valve anc Safety Valve Failures and Cnallenges," March 26, 1982.

11. S. A. Varga, NRC letter to F. L. Clayton, Alabama Power Comoany, "C:moletion of NUREG 07371: ems II.K.3.9, II.K.3.10 and II.K.3.12,"

January 6, 1982.

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n en U.S. NUCLE AR REGUL ATC Av CCNMIS$1CN BIBLIOGRAPHIC DATA SHEET EGG-EA-6431 A Ti?LE ANC SL87:TLE 2. : Lee.e 0,,,ei CONFORMANCE TO NRR GENERIC LETTER 82-16 JOSEPH M. FARLEY NUCLEAR PLANT UNITS 1 AND 2 3 ECi,,ENT s ACCESS.eN No 7 AU TMC R'S' 5 OATE AE80 AT CCVPLETED ucNrw l vt AA D. M. Beahm October 1983 a ,EarcaviNG caGAm:ATICN N AVE ANO V A4UNG ACORESS uncNar 2 0 CJoel QATE REPORT ISSUED voNim (vtAn October 1983 EG&G Idaho, Inc. . 7c , ,,, ,,,, , ,

Idaho Falls, ID 83415 8 ! Leave sann o 12 $PONSOR 6NG ORG AN.2 ATION N AVE ANO '.t Alu NG ACORESS < tac uoe t o Codes Division of P.oiect and cesidant o ec. m oecinn tI ii riN No U.S. Nuclear Regulatory Commission i

• C i Atlanta,beorq1a101 Marie ta Stree3030auite 2900 13 T'r PE OF REPORT og mic o g g9g mg g fjagss , ,, g,gy, j 15 $uPPLE'. TEN TA Av NOTE S 14 stas,e massi 16 ABSTa ACT 200 woras or essi This EG&G Idaho, Inc., report evaluates whether the designated Operating Reactor Plant has conformed to the requirements of the NRR Generic Letter No. 82-16, "NUREG-0737 Technical Specificatiins."

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is av A L AsiuTv STATEvENT r a sE: am 2.2ss r., e,- .o ;,aA;Es Unclassified l:3 _

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