ML19343B579

Informs That Review Process Is Continuing to Compare Various Aspects of New Criteria Contained in NUREG-0737 W/Existing Positions.Comments on Positions Identified in NUREG-0737 Encl

ML19343B579
Person / Time
Site:	Pilgrim
Issue date:	12/15/1980
From:	Morisi A BOSTON EDISON CO.
To:	Eisenhut D Office of Nuclear Reactor Regulation
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-1.A.1.1, TASK-2.K.3.27, TASK-TM 80-310, NUDOCS 8012240272
Download: ML19343B579 (95)

Text

4

.l BOSTON EDI5O N COMPANY GENERAL OFFtCES S00 WOvLSTON STmEET WOSTON, M AmeACHLS ETTS O2199

~ ~ ' ' ' '

A. V. M O Rt 31 MANAGER NUCLEAR OPERATIONS StjPPORT DEPARTMENT

~ O December 15, 1980 BECo. Ltr. #80-310 Mr. Darrell G. Eisenhut, Director Division of Licensing U. S. Nuclear Regulatory Commission Washington, D. C.

20555 License No.

DPR-35 Docket No.

50-293 NUREG 0737 Post TMI Requirements

References:

Attachment A

Dear Sir:

In your letter of October 31, 1980 (reference K) you requested all operating reactor licensees to implement the actions contained in NUREG 0737 in accordance with criteria and schedules established therein.

As you recognized in your letter, Boston Edison Company has proceeded with the implementation of many of the items in accordance with previous NRC letters dated September 13, 1979, 4

October 30, 1979 and September 5, 1980.

Upon receipt of reference (K) we redirected engineering efforts where possible and initiated an engineering review process to compare the various aspects of the new criteria with our existing positions.

However due to constraints l

imposed on our staff by previous connitments and the limited experienced external resources available at short notice, our review is continuing i

as of this date. Therefore relief from various aspects of the I

clarifying criteria in NUREG 0737 may be required, for those items that have been completed or are in the implementation phase, when our review is completed.

In Attachment B to this letter, we have addressed each of the positions identified in NUREG 0737. An asterisk adjacent to the requirement description signifies that the item is involved in the ongoing review process. Your staff shall be appraised of any deviations which may arise from the established criteria or implementing dates as soon as that infonnation becomes available.

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e COUTCN EoISCN COMPANY I

i We trust this letter -is responsive to your needs, however should you require any additional infonnation please do not-hesitate to contact us.

Very truly yours, A. V. Morisi

'?

Comonwealth of Massachusetts)

County of Suffolk

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l Then personnaly appeared before me A. V. Morisi, who, being duly sworn, j

did state that he is Manager-Nuclear Operations Support Department, the applicant herein, and that he is duly authorized to execute and file the submittal contained herein in the name and on behalf of Boston Edison Company and that the statements in said submittal are true to the.best of his knowledge and belief.

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My Comission expires:

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'~3[n%- k. LO Notary Public f i

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o ATTACHMENT A REFERENCE 3 Reference (A)

BECo Letter #79-206, dated October 19, 1979, " Follow-up to reviews regarding the Three Mile Island Unit 2 accident.

Reference (B)

BECo Letter #79-241, dated November 21, 1979, response to discussion of Lessons Learned Short term requirements.

Reference (C)

BECo Letter dated December 31, 1979, response to lessons Learned Short term requirements.

Reference (D)

BECo Letter #80-54, dated April 4,1980, implementation details of Lessons Lcarned short term requirements.

Reference (E)

BECo Letter #80-285, dated November 6, 1980, "NUREG 0578 Implementation."

Reference (F)

BECo Letter dated October 15, 1980, response to interim Criteria for shift staffing.

Reference (G)

NRC Letter dated November 18, letter - three TMI items.

Reference (H)

BECo Letter #80-268, dated October 29, 1980, Status of NUREG 0578 Cat B ltems.

Reference (1)

NRC Letter dated May 12, 1980, " Amendment #42 to 0. L.

1. CPR - 35".

Reference (J)

GECo Letter dated, October 1,1980, " Implementation details of TMI Action Plan Requirements."

Reference (K)

NRC Letter dated, October 31, 1980, " Post TMI Require-ments." (0737) l l

Reference (M)

G.E. Letter MFN-117-80 to NRC, "NUREG-0578 Requirement 2.1.9 Implementation by BWR Owners Group."

Reference (N)

NRC Letter dated, December 18, 1979, "NxC Staff Evaluation of BECo response to IE Bulletin #79-08."

Reference (0)

Pilgrim Nuclear Power Station Unit 1 Emergency Plan trans-l mitted via BECo Letter #80-116 dated July 1,1980.

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4 ATTACletENT B q

NUREG 073 Position Descriptions 4

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ITEM NtM fR TITlf (4SCRIPTION iP4' LIP 4 NTATl0N Sulffilll f RFSF'ONSr t

f.A.I.

Shift

1. On duty 1/1/80 Boston Edison believes that the STA program described in Refeconee (0) i technical satisfied the intent of 0578 Item 2.2.lb and 0757 item 1.A.I.l.

4 advisor Subsequent reorganization within the tJuclear Organliation has modified the description provided in Reference (D).

A re-J i

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.vlsed program description will be Incorporated in our 1/1/81 response to I.A.I.I.4.

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2. Technical lI/15/80 Boston Edison will reevaluate and reissue our position in specifications Reference (E) per request of your staff.

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3. Trained per 1/1/81 A description of the current.tralning program and demonstration of LL Cat B con,formance with the October 30, 1979 letter will be submitted by January 1, 1981.

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4. Describe long-1/1/81 A description of the long term STA program will be submitted by term progrem January l,1981.

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ITfM NIMIER Tlit r DESNtlPTIOP4 IWlIMf NTAll(te SOflRil f RFSPfWSF l.A.I.2 Shift supervisor Delegate non-1/1/60 Boston Edison believes the response transmitted to responsibilities safety duties t1RC by Refeience (D) satisfles this requirmnt.

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ITfM tm M fR TITLE OfSCRIPTION IM't if4NTATION Sniflulf f RfSPONSF I.A.l.3 Shift manning

1. Limit overtime 11/1/80 Ibston Ediston has estabitsbed an overtine policy for llconsed operators which satisfies the objective of "

this requirement. The polley will be formally ad-dressed in station procedures by January 16, 1981 I

1his polley is not applicatde to non-ilcansed per-

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sonnel.

2. Min shift crew 7/1/82 Ik)ston Edison believes its response contained in Reference (F ) satisfles this HRC requirement. Technical Specifi-cation change will be submitted in conjunction with tre t

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Implementation date.

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l.A.2.1r Innediate upgrad-

1. SRO experience 5/1/80 TNPS training manual has been revised to satisfy this i

Ing of RO and SRO requirement.

training and qualifications

2. SROs be R0s for 12/l/80 PtOS tra ining manual has been revised to require appil-I yr cants for Si@s license to have been a licensed FO for one year.

3. Three months 8/l/80 PNPS t raining manual has been revised to satisfy this on shift requirement.

4. Modify 8/1/80 FHPS training department has submitted a revised train-training Ing program to the OtB. Training for mitigating core damage will be addressed in response TAP ltem 11.B.4.

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5. Facility 5/1/80 PHPS t raining manual has been revised to satisf y this certification requirement.

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1. 58 LOCA 6/1/80 This 8 tom is complute. Procedures appilcable to $3 IJEA acclaent have been revised and operator training has been completed e

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Boston Edisons responso In Reference 10) and subsequent 1&L and procedurus

,m slie inspections satisfy this requirement, review

2. Inadequate Ikhton Edison Company supports the UWR owners group pos-core conting Itlon on items I.C.I.2 and 1.C.l.3.

Emeroency procedure

c. Roanalyze and propose 1/1/81 guidelines were sutsmitted to the NRC in Reference (M).

guldelines f ollowing P&C Prelmplementation review, emergency proco-

k. Ruvise First refueling outage dure revisions and operator training will proceed in accor-procedures after I/l/82 dance with the schedule established in NUREG 0737.

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accidents

a. Roanalyze and propose 1/1/82 guidelines

b. Revise pmcodures First rvfueling outage after 1/1/82

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I Tf M NtFbf R TITLE OrSCRIPTim IMPt emf NTATirti sairrwie r prc,ponc,r t

I.C.2 Shift & relief implement shift 1/1/80 in Roterance ([3, Edison stated it station proce-turnover proco-turnover checklist dure 1.3.18 has been revised to assure the continuous dures transmittal of operational Information and status of systems essential to the prevention and mitigation of

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an accident or transient. During a site inspection by the l&E representative during the week of t4ovember i

i 1 no system had been established to periodically review the ef fectivuness of the shif t turnover procedure. M that time, Boston Edison committed to have a system in place

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by January 1, 1981, so that this NRC requirement will be i

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_lRtLUMtif R TITIE OFSCRIPTION DCI(Mf tJT ATintJ c04 0ut F orsmer I.C.4 Control-room,

Establish authority, 4 /l /ti()

Rnton Edison teelieves response suteltted to t4RC in access limit access fieteronce (D) satlstles trie control roarn access roquiremont.

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) I ITEM NtM TR TITtE DESCRIPTION IMPI f Mf NT ATI0ta Saff0 tit f HE W1NW

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3.D.I Control-room Preliminary TBD Uoston Edison Company is participating in the BWR owners design reviewI assessment and group survey program presently in progress. When further j

schedule for NfC criterla (Nt1HEG 0700) is available, a comparison of

' i' correct ing the two programs will be made.

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/Y ITEM NtM VR TITLE DESCRIPTION lMPIFMENTATION SrM DutF RfSPONSE 100.2 Plant-safety-

1. Description TUO Boston Edison Ccapany has subscribed to the OWR owners

, parameter display group effort for SPDS development. Boston Edison will cx>nsole develop an Installation schedule following publication tAJRLG 06%,

2. Installed TOD

3. Fully TBD laplemented 4

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o ITEM Ni m fR TITLE OfSCRIPTlON 1WI f Mf NTATlOtl SCHf fait E FESP0t4%f j

13.8.1 Reactor-coolant-

• l. Design vents 7/1/81 lbston Edison believed the responso provided in systere vents Reference (A) satisf ied the fil#tfG-0578 2.1.9 NtW 4 requiremont, in Reference (A) Edison conunitted to address the effect of non-condensibles on the opera-tion of the HPCl/HCIC systems. The BWR owners group l

provided a response verifying the operation of the

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HPCl/ACIC systems with the presence of non-condensibles in the sfeam system supply. Boston Edison will review the owners group response to determine applicability l

to INPS.

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2. Install vents 7/1/82 (LL Cat B) 1 T

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3. Procedures 1/1/82 i

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fl.D.2 Plant shielding

'l. Rovlew designs 1/1/80 in early 1980, a shleiding review of Pilgrim Station was comnieted and eesults forwarded to the NRC Referenet (D).

I Since that submi t tal, significant disctf iun and clarlfi-I cation regarding this item have taken place. Boston Edison Is presently reanalyzing'its shleiding on the basis of this

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new Information.

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2. Plant modifications 1/1/82

. Plant modifications have begun and further modificata j

(LL Cat B) lons will be evaluated on the basis of the results of the shleiding reanalysis presently in proqress.

t It is enticinated that necessary plant modifications will be completed by January 1,1982.

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3. EqulPrent 6/ 30/82 This item has been addressed in DECO's response to lE

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qualif! cations Bulletin 79-01B, Future requirements for equiprent qualification will be addressed in accordance with mod-Ifications to our operating license initiated by HRC.

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/7 lifM NUMBER TITIE OFSCRIPTION IWt FMINTAT10t4 SOff Dillf RE',PONSF l

l II.B.3 Post-accident

1. Interim system 1/1/80 As a result of an I&E site inspection poston Edison l

sampling was required to implement procedure (s) for takinq and handling a containment atmospheric sample by November 28, 1980 Station Procedure 7.4.17 was revised and approved i

to satisfy this requirement.

d "2. Plant modifications 1/1/82 Hoston Edison believes that the Post accident psepling (LL Cat 8) system as described in Ref erence (D) satisfies the recuirement of PAJREG 0737 ltem l1.0.3.2.

System operetbon is tent e tively scheduled for June 1981 and a letter of conformance will be submitted by January 1,1982. As a result of ISE Inspection, Doston Edison was required to t. ave in place procedures for taking and handling a containment atmosphere sample. Procedures have been Implemented to accomplish this.

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ITm psfR TITLE MSCR f PT im im m mm ng r 11.8.4 Training for '

l.' Develop training 1/1/81 poston Edison's training program for mitigating core mitigating program damsge Is in its final stages of development and should core damage be complete by January 1,1988.

2. Implement 1/l/Bl The initial program is scheduled for presentation to PrFS program personnel commencing February 3, l981.

a. Initial 4/1/88

b. Complete 10/1/81 f

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ITEM ta M KR TITLE DESCRIPil0N IMPt i Mt NT AT ION SCHf t' ult F RfSPONSE ll.D.1 Rollef & safety

1. Submit program 1/1/80 Boston Edison subscribes to the BWH owners group position valve test on Safety and Rollef Valve testing. On September 18, t

requirenants 1980, the DWR owners group submitted the Safety / Relief Valve test description to the NRC.

It is anticipated that testing and preparation of a plant-specific report 3 '

will proceed in accordance with the schedule established in NUREG 0757.

2. RV & SV testing (LL Cat B) i

a. Complete 7/1/81 testing

b. Plant-10/1/81 specific report

3. Block-valve 7/1/82 This Itum is not applicable to PHPS.

i testing 1

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Indication Indications of Indication syslum descr.lbgd in Reference (D) j valve position satisfied the NUREG 0578 2.1.30 requirement, t

Selsmic and environmental quellfication for system components is presently in progress and will be available in early 1981.

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Doston Edison will reevaluate and reissue our 2 Technical 12/15/80 post tlon in Reference (O per request of your specttIcations stoff.

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RESPONSE

ITEM NLDUER f

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. Auxillary

1. Short fem 7/1/81 Not applicable to IMR.

).1 feedwater system j

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2. Long tem l/1/82 Not opplicable to BWR,

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1. Initletion Not applicable to OldR.

t water system

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b. Safety grade 7/1/81

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a. Control 7/1/80 grade-l j

b. LL A Technical 12/15/80 i

specifications

.c. Safety grade 7/1/81 t

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1 TIM NittnER TITtE f(srRIPTION I WLFMfNTATION sritffoif PrSPONSF IloE.3.1 Emergency power

1. Upgrade power 1/1/80 tbt applicable to owr, for pressurizer supply heaters

2. Technical 12/15/80 Not appilcable to DWR.

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1 TE M Nt *tsF R TlTLE DE SCHIPT IO4 IMPI f Mt NT AT 104 SOtt la st f RfSP0tiSE 11.E.4.2 Contai nnent 1-4 Improve diverse 1/1/80 Boston Edison believes that its response in Reference (D),

j isolation isolation aduquately satistles NRC criteria. l&E site Inspection i

dependability the week of teoventer 2 revealed a problem with the opera-f tion of control s=liches for containment vent and nitrogen

[

makeup valves. The control switches have been modified to i

allow operation between the "open" and "close" position without a key and require a key to get in the " Emergency 3

J open" position.

5. Containment pressure setpoint Boston Edison will respond by January 1,1981.

I

a. Specify pressure 1/3/81 I

b. Hodifications 7/1/81

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6. Containment valves 1/1/81 Boston Edison will respond by January I,1981.

1 i

7. Radiation signal 7/1/81 Boston Edison is participating in the DwR owners group i

on purge valves effort presently under development. Initial Indications l

on material delivery dates and design criteria clarifica-tion place the July 1, 1981 Implementation data in jeopar-1 dy.

Once the design details and equipment specifications are available, Edison will develop en Implementation sche-l 1

dule to satisfy this requirement.

I i

Technical Specifications issued by the Commission i

j

8. Technical specification 12/15/80 Reference (1), contains the basis for our posttlon f

on this requiroment.

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! TEM NtiSOFR TITlf DfSCHIPfl0H f ret f MENLinan Ecitrmt r pripora

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1. tbble gas 1/1/82 Iloston Edison believes the modification described in a

monitor Reference (D) satistled the Intent of ta) REG 0578 Item j

2.I.ub for the Cat A requirement. I&E sita inspection 3

4 the week of Novteber 2 discovered station procedures for the conversion of er/hr to cl/sec were not in place. Boston Edison has Impfeh nted procedures to i

I satisfy this requirement. Ooston Edison also bellowes the Cat A modification will satisfy the January 1, i

1962 requirenent with slight modifications to the j

installed system. This position has been discussed with your staf f and tentative agreenent reached. We will provide detalled Justification for this position by January 1, 1982.

j "2. lodine /porticulate I/1/82 Station procedures presently exist describing the tak-samplin9 Ing and handling of lodine / particulate samples under normal conditions. These procedures will be adhered i

to followlag an accident if a health physics survey i

allows access to the sample points. If unaccessible, the Installed noble gas effluent monitor described in Item I could be used to estimate lodine releases. In 1

addition, Boston Edison will review the requirement for lodine and particulate sampfirtj contained in 0737 z

and reconenended changes to hardware and procedures (if anyl to satisf y the requirements will to com-plated by January 1,1982.

I i

2 1'

'3. Containment high-range 1/l/82 A containment high range radiation monitoring system i

radiation monitor which Boston Edison believes meets the requirements of 4

tRJREG 0578 2.l.88 Is tentatively scheduled for opera-

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tion by January 1,1982 final design details are scheduled to be available for review by July 1, 1981 j

"4. Containment pressure 1/1/82 A containdent pressure monitoring. system *Sich l

Doston Edison t,elleves meets the requirements of NUREG 0578 Item 2.l.9 and NL4<EG 0737 Item II.F.I.4, is ten-tatively scheduled for operation on February 1,1981.

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ll.F.l Accident-aqpitoring

'5.

Containment 1/l/82 A containnasnt water level monitoring systa which l

(continued) water level Ebston Edison believes meets the requirements of I

M1 REG 0578 Item 2.l.9 teEW 2 is tentatively scheduled for operation on February 8,1991.

l,

'6. Containmenf 1/1/82 fWS I is currently Installing a containment hydrog(o hydrogen and oxygen monitoring system which is tentatively scheduled for operation in June 1981. Boston Edison j

believes that the HA monitoring systen as described in Reference (D) tultills the requirements of NUREG 1

0578 Item 2.1.9 HEW 5.

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1 OfSCRIPTION IWif MINTATION Sniffullr Rf SIMV ITEM NtMOER TITtE ll.F.2 Insturmentation

1. Subcool meter 1/1/80 This item is not applicable to PPPS.

for detection of Inadequate core cooling i

I

2. Technical specifications 12/15/80 As stated in Raterence (E), technical specifications (LL Cat Al changes are not considered appropriate for item ll.F.2 at this time.

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• 3. Install level 1/1/82 As stated in Reference (H), "tsaston Edison concurs with instruments the IMR Owners Group posIflon that existing Instru-(LL Cat M mentation is adequate for detecting Inadequate core l

cooling." Boston Edison is, however, evaleating I

measures for improving its reactor vessel water t

j level Instrumentation.

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II.G.I Power supplies

1. Upgrade to 1/1/80 Although, this item is not applicable to (MR's a letter dated I

for pressurizer emergency sources Novemt,or 14, 1979 frca D. Eisenhut to T. Dennan, requested all

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relief valves, tMl's requiring instrument air to operate SRV's to verif y that block valves, and the instrumunt air supplies to SRV's can be manually connected level Indicators to an energency power source. Hoston Edison provided this l

Information in Reference (C).

In 14sf erence (Cl, it was stated that 3 of 4 air co g ressors are automatically reenergized after initial lood shedding upon loss of offsite power. Upon sut,sequant review, it was discovered that the air compressors do not automatically reenergize but could tre manually con-nected to en emergency source of power.

2. Technical 12/15/80 Not applicable to PNPS.

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i ITEM NIM (R TITLE DETRIPTION IWifMINTATiflN TilfDif f RISFf#M I I. K. 2 Orders on B&W*

8. L$ grade AfW See ll.E.8.8 Not applicable to B#t.

plants system I

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mechanical 1

report I/1/82 i

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1 TEM enM1f R TlTtF Of TRIPT ION IWifMfNI AtlOta SOffTHit f Pf5PONSF II.K.2 Orders on B&W,

14. Lift See Not applicable to HWR.

plants (continued) frequency of II.K.3.7 PORVs & SVs

45. Effects of Cumplete Not applicable to OWH.

slog flow on OTSGS

16. RCP seal Ccaplete Hot applicable to BWR.

damage

17. Volding in

a. Con.

Not applicable to BWR.

ICS plate

b. 1/1/82

89. Benchmark

a. Coe.

Not applicable to BWR.

f analysis of plate seq. AfW flow

b. 1/1/82

20. System re-Complete Not applicable to f4R.

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ITFM telMfR TITLE Of SCRIPTinti IMPt f MitJTATlati snif foir prvarnw e

it K.3 Final recommenda-

3. Reporting SV & RV l/l/81 Boston Edison well submit a report detalling failures and tions, IMO task failures & challengus challengos to SRV's since April of 1980 by January 1,1981 forco o

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b. Modify 3/1/82

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11.K.3 Final recommunda-

7. Evaluation of POtV I/l/88 Not applicable to BwR.

tions, 850 task opening iorce probablllty i

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f ITEM Ntit0ER TITlf DE SCRIPT IO4 iMPt FMINT AT IO4 50tF Dtil I R(spot 45r 11 K.3 Final recommundptions

11. Justify use Plant tiot applicable to owr.

Da0 task force of certain specific (continueJ) 00RV t

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,_ _ _ M$PCHSE 1

l li.K.3 Final recomunendations

12. An+1cipatory Not applicable to EMR.

O&O task force

. trip on

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(continued turbine trip

a. Confirue-t/1/81 3

tion or pro-i~

pose modif1-catlons a

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ITEM tit $tif R TITlf DFSCRIPTIO4 IkFl f tt t4T AT inti 50 tf Dtil F Rf5Por4SF Final recommend 14 Iso condenser 1/1/82 II.K.3 b10 tasn force,ations Not appilcable to it4PS.

I Isol anMI-(continued) fication I

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a iiE4 NtNEfR T1TLE OESCR1PTlON IWt Ett NT AT10H SOffW tti Rf SPop4SF ll.K.3 Final recommendations

15. Isolation of 7/1/81 (MR owners group has Jeweloped a conceptual design IMO task force itPCI & ICIC to s.itisfy this requirement. Boston Edison is (continued) modification developing a design package to implement this in

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accordance ulth the NfC's schedule. Should any Problems arise we will advise you lammediately.

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II.K.5 Final recoseendations

16. Challenges 4 floston Edison in conjunction with the BWR owners group is 840 task force failures to prepar!ng a feasibility study for reducing SRV challenges (continued) relief valves which will include recomunended Mlfications (If required)

a. Study 4/1/81 for reducing $RV challenges. This study is scheduled for

b. Modify 1st refueling outage sutalttal to the staf f by April I,1988 or 1 yr after approval 4

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RESPONSE

11.K.3 Final recosamen4stions

17. [CC system 1/l/81 Doston Edison is presently preparing the ECC system outage

'j B40 task force

. outages report, which is scheduled for submittel to NHC by January (continued) 1, 1961.

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ll.K.3 Final reconsnandations

18. ADS actuation Boston Edisog in conjunction with the EfMR owwr s grouq le e

B40 task force

a. Study 4/1/8l preparing a feasibility study scheduled for sutwnlitel to

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(continued)

b. Propose 4/8/82 the NF4C staf f by April 1,1968.

c. Modifica-1st refueling outage tion 6 m) after statt approval t

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19. Interlock 7/1/81 Not applicable to Pt#'$.

B10 task force recirc pump (continued) modification e

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20. Loss of SVC 7/1/88 Not applicable to PrM.

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j ll.K.3 Final reemdations

22. HCIC suction Ooston Edison is presently evaluating the feestbility and

^

B&O task force

a. Ver8fy 1/1/81 enhancennent of safety that would be gained by implementing (continued)

b. Modification 1/1/82 this requirement. It af ter this evaluation is complete, Edison has Jetermined ihls modification elli enharge the safuty of it4 plant every attempt will be made to satisfy the NAC schedule.. in the Interim, EEco will verif y that existing procedures exist for the manual sultchover of the ACIC system suction from the condensato storage tank to the suppression pool.

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dations

24. Space cooling 1/l/82 tbston Edison, in conjunction with tre Owet owners 840 task force for it'C1/RCIC group, will evaluate the capability of the 11PCI and (continued) modifications RCIC systems to withstand a crumplete loss of of fsite alternating current power to their support systems, including coolers, for at lesst two hours. Modi f Icat im required es a result of the evaluation will be imple-mented on en expedited schedule and any deviation from the NRC schedule will be brought to your attention Inunedtately.

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27. Common reference 7/1/81 DWR owners group has developed a generic response to this Ba0 task force level requironwnt. Roston Edison will review the response end (continued) determine its appilcability to Pff'S by July 8,1981.

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ITEM Ntf 0f R TITLE prscpipy g ga ppgggg RFSPOt4SE ti,K,3 Final reccrmnpations

29. Performance 4/1/81 Not opp llcable to PNPS.

9 B&O task force of Isolation 3

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11.K. 3 Final reconsnen8ations

30. SB LOCA Boston Edison believes It has adequately responded to this i l B&O task force methods question in Reference (J).

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(continued)

.a. Schedule 11/IS/60 8

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b, Model I/1/82

c. New l/1/83 or j

analyses 1 yr after 5

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i ll.K.3 Final reconsnendations

31. Compliance 1/l/85 or Af ter completion of II.K.3.30 by General Electric, Boston B&O task forc's with CFR 50.46 i yr Edison will determine applicability to it4PS and advise the 4

(continued) af ter statf NRC.

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45. Effects of See ll.K.2.15 Hot a>plicable to twR.

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II.K.3 Final reconenendations

45. knual depres-t/1/81 M w ners group has developed a generic porltion in 080 task force

• surization response to this reqtsf rement which ibston Edison 'is p

(continued) reviewing and will submit it's evaluation by January 1,

1981, O

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i ITEM NLM WR TITLE DESCRIPTION IMPtEMENTATION SCHFrullE RfsPONSF i

e' 11.K.3 Final recommendations

57. Identify water TD0 This requirement has been incorporated into the emergency B&O task force'

. searces prlw to procedur e guidellr.es which have been developed anJ submit-(continad) actuation of Auto

• ted to the NHC consistent with the requirement of 1.C.I.

m.itic Depressurization 1

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ka ll ITEM NIM ER TITi f fiFSCRIPTION IWt FMINT ATION SCHIDut f RFSPONSF l

l til.A.I.l Emergency Short-term The initial upgrading of the plans has treen completed h

preparedness, leprovements Complete (see Docket 6 0-29M and an NRC review performed. Based

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short term upon that review and a meeting with NRC staf f on Ducentier 8, 4

l 1980, further modifications to the plan are underway.

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ITEM NIMtFR TITLE DESCRIPTION lMPt fMf NTATION SMtf full f RfSPONSE III.A.I.2 Upgrade emergency

1. Interim TSC Complete As stated in N forence (D), an Interim TEC and OSC have been estab.

support facill-OSC & EOF lished and are operational at Pilgrim Station. Tr.e Interim EOF is g

ties expected to be fully operational by March 1,1981.

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2. Design TBD ltem lit.A.I.2 will be addressed when additional clarification has j

been provided by NUREG-06%.

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3. M>difications 100 ltem lit.A.I.2 will be addressed when additional clarification has been provided by NUREG-06%.

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g ITEM MM3ER TITtr DESCRIPTION IMPlfMfNTATION SCM DHiF RFSDONSF lil.A.2 Emergency

1. Upgrade amor-All of the critoria of NUREG 06S4 will be fulfillutt with the

'j preparedness '

gency plans 4/1/81 Possible exception of Appendix 2 and/or vendor's Inability to App. E, to supply equipment, and all implementation deadlines will be 10 CFR 50 met.

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2. Meteorological 4/l/81 We are presently evaluating the technical feasibility and de's cost'of equipment and systems which will fulfill the functional requirements of this section. We do not believe that it will be possible to achieve full compliance by April I, 1981.

4 Equipment presently exists at PHPS which may be reconfigured to essentially fulfill these requirements (with the exception of the class 8 modell. Location end proper configuration of this equipment is being evaluated at this time. To the extent Possible, modifications to existing systems will be made to fulfill these requirements prior to April I, 19ul and a schedule will be submitted when one becomes available. Final criteria for EOFs (NUREG 06%I when issued may impact the implementation dates.

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Rf SIW4SF ITE M Nt*OER TITtE (fSCRIPTIOJ IWlf M NTATIO3 SCliffWil E 5

f Ill.D.I.I Primary coolant

1. 1. Leak reduction Complete Ooston Edison has implemented the requirements of this outside containment Itum by Instituting a leak reduction progrom described in Reference (D1. During an l&E site inspection, one of the surveillance procedures had been retired 1510TSI and another had not been scheduled. DECO took immedlate I

l action by perf orming the procedure that had not beer. done j

and justifying to the satisfaction of the site representa-tive the retirement of the 58GTS surveillance procedure.

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2. Technical 12/15/80 Ibston Edison will reevaluate and rolssue our position fri specification Reference (E) per request of your staf f.

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ITEM NUM8fR TITLE OfSCRIPTION 14 M MENTATION SCllEEUtE

RESPONSE

i III.D.3.3 inplant redletion

1. Provido means Comple' a Boston Edison believes that modifications to procedures a

monitoring to determine and training in conjunction with procurement of equip-1 presence of ment as stated in Reference (D) satistled the intent of NUREG '

I radiolodine 0578 Item 2.1.8c and NUREG 0660 Item lit.D.3.3.1 and

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NUREG 0737 Ill.D.3.3.2.

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2. M>difications 1/1/81 Doston Edison response to item 1 also satisfied this to accurately requirement.

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-TITtE OESCRIPTION 1Wt[MFNTAT1083 Snifruit f-RfSP0t4SF 1

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lit.D,3.4 Control-room

1. Review 1/1/81 Boston Edison will submit its study and proposed modift-l habitability cations by January 1,1981.

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2. Modification 1/l/83

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