ML20012F264

Summary of 900305 Meeting W/Util in Rockville,Md to Discuss Topics of Interest to Util & Nrc,Including Status of Millstone Unit 2 Containment Isolation Valve Review & Millstone Unit 1 Degraded Grid Issue.Attendee List Encl

ML20012F264
Person / Time
Site:	Haddam Neck, Millstone  File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	03/28/1990
From:	Jaffe D Office of Nuclear Reactor Regulation
To:	Office of Nuclear Reactor Regulation
References
NUDOCS 9004110038
Download: ML20012F264 (37)

Text

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6 March 28, 1990 Docket Nos. S0 213/245/336/423 LICENSEE:

Northeast Utilities FACILITIES:

Haddam Neck and Millstone Units 1,2 and 3

SUBJECT:

TOPICS OF INTEREST TO THE NRC STAFF Al'D NORTHEAST UTILITIES On March 5,1990 representatives of Noitheast Utilities (thc lictnsce) and the HRC Staff met in Conference Room F.21 of the White Flint Building in Rockville, Maryland.

A list of attendees is contained in Enclosure 1.

P The NRC Staff indicated that the purpose of the meeting was not to resolve technical issues but rather to generally discuss items of interest. The licensee reviewed the progress of a number of importent reviews on Haddam Neck and Millstone Units 1 2 and 3.

In addition, a number of upcoming submittals were described by the licensee. A description of the licensee's presentation is contained in Enclosure 2.

One item of particular interest to the licensee and the NRC Staff is the status of the Millstone Unit 2 containment isolation valve review.

The valves of interest are associated with the Reactor Building Closed Cooling Water (RBCCW)

System. The licensee had not been treating the subject RBCCW valves as containment isolaticn valves with regard to local leak rate testing (Type "C" testing per Appendix 0 to 100Fh Part 50).

The NRC Staff stated that the valves must be Type "C* tested unless the licensee receives an exemption from Appendix J.

The staff further stated that a prelimintry review of the RBCCW System inside containment indicated that exemption from Appendix J weuld most i

likely be granted; however, the licenste must take the initiativc with regard to an application for exemption.

/s/

David H. Jaffe, Project itanager Project Directorate 1 4 Division of Reactor Projects. 1/11

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)ISTRIBUTION FOR MEETING St!MMARY_ DATED: Match 28, 1990

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Plant File J. Stoir S. Norris OGC E. Jordan (MilBB3302)

NRC Participants M. Boyle D. Haverkamp D. Jaffe C. McCracken J. Pulsipher J. Stolz A. Vegel G. Vissing A. Wang J. Wermiel ACRS(10)

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UNITED STATES 8

NUCLEAR REGULATORY COMMISSION r

s wa Hmotow. p.c. mas March 28, 1990 Docket Nos. 50-213/245/336/423 LICENSEE:

Northeast Utilities FACILITIES:

Haddam Neck and Millstone Units 1,2 and 3

SUBJECT:

TOPICS OF INTEREST TO THE NRC STAFF AND NORTHEAST UTILITIES On March 5,1990 representatives of Northeast Utilities (the licensee) and the NRC Staff met in Conference Room F 21 of the White Flint Building in Rockville, Maryland. A list of attendees is contained in Enclosure 1.

The NRC Staff indicated that the purpose of the meeting was not to resolve technical issues but rather to generally discuss items of. interest. The licensee reviewed the progress of a number of important reviews on Haddam Neck and Millstone Units 1, 2 and 3.

In addition, a number of upcoming submittals were described by the licensee.

A description of the licensee's presentation is contained in Enclosure 2.

One item of particular interest to the licensee and the NRC Staff is the status of the Millstone Unit 2 containment isolation valve review. The valves of interest are associated with the Reactor Building Closed Cooling Water (RBCCW)

Sys tem. The licensee had not been treating the subject RBCCW valves as containment isolation valves with regard to local leak rate testing (Type "C" testing per Appendix J to 10CFR Part 50). The NRC Staff stated that the l

valves must be Type "C" tested unless the licensee receives an exemption from Appendix J.

The staff further stated that a preliminary review of the RBCCW System inside containment indicated that exemption from Appendix J would most likely be granted; however, the licensee must take the initiative with regard to an application for exemption.

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1 David affe.vroject Manager Project irectorate I-4 Division of Reactor Projects - I/II

Enclosures:

As Stated cc w/ enclosures:

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l Mr. Edward J. Mroczka Millstone Nuclear Power Northeast Nuclear Energy Company Station Unit Nos. 1, 2 & 3 i

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CC*

Gerald Garfield, Esquire R. M. Kacich, Manager Day, Berry and Howard Generation Facilities Licensing Counselors at Law Northeast Utilities Service Company City Place Post Office Box 270 Hartford, Connecticut 06103-3499 Hartford, Connecticut 06141-0270 W. D. Romberg, Vice President D. O. Nordquist

)

Nuclear Operations Director of Quality Services Northeast Utilities Service Company Northeast Utilities Service Company Post Office Box 270 Post Office Box 270 Hartford, Connecticut 06141-0270 Hartford, Connecticut 06141-0270 Kevin McCarthy, Director Regional Administrator Radiation Control Unit Region I Department of Environmental Protection U. S. Nuclear Regulatory Comission State Office Building 475 Allendale Road I

Hartford, Connecticut 06106 King of Prussia, Pennsylvania 19406 Bradford S. Chase, Under Secretary First Selectmen l

Energy Division Town of Waterford i

Office of Policy and Management Hall of Records 80 Washington Street 200 Boston Post Road Hartford, Connecticut 06106 Waterford, Connecticut 06385 S. E. Scace, Nuclear Station Director W. J. Raymond, Resident Inspector Millstone Nuclear Power Station Millstone Nuclear Power Station Northeast Nuclear Energy Company c/o U. S. Nuclear Regulatory Comission l

Post Office Box 128 Post Office Box 811 l

Waterford, Connecticut 06385 Niantic, Connecticut 06357 l

C. H. Clement, Nuclear Unit Director M. R. Scully, Executive Director l

Millstone Unit No. 3 Connecticut Municipal Electric Northeast Nuclear Energy Company Energy Cooperative 1

Post Office Box 128 30 Stott Avenue Waterford, Connecticut 06385 Norwich, Connecticut 06360 Ms. Jane Spector Michael L. Jones, Manager Federal Energy Regulatory Commission Project Management Department 825 N. Capitol Street, N.E.

Massachusetts flunicipal Wholesale Room 8608C Electric Company Washington, D.C.

20426 Post Office Box 426 Ludlow, Massachusetts 01056 l

Burlington Electric Department c/o Robert E. Fletcher, Esq.

271 South Union Street Burlington, Vermont 05402

l

2 Mr. Edward J. Mroczka Millstone Nuclear Power Northeast Nuclear Energy Company Station Unit Nos.1, 2 8 3 J. P. Stetz, Nuclear Unit Director J. S. Keenan, Nuclear Unit Director Millstone Unit No. 1 Millstone Unit No. 2 Northeast Nuclear Energy Company Northeast Nuclear Energy Company Post Office Box 128 Post Office Box 128 Waterford, Connecticut 06385 Waterford, Connecticut 06385 Charles Brinkman, Manager Washington Nuclear Operations C-E Power Systems Combustion Engineering, Inc.

12300 Twinbook Pkwy Suite 330 Rockville, Maryland 20852 O

I 1

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i l

l ENCLOSURE 1 I

ATTENDANCE LIST i

NRC STAFF M. Boyle D. Haverkamp D. Jaffe C. McCracken -

J. Pulsipher J. Stolz A. Vegel i

G. Vissing A. Wang J. Wermiel NORTHEAST UTILITIES P. Blasioli R. Joshi R. Kacich E. Perkins 1

9 1

c L.

r 9

4 l

ENCLOSURE 2 I

Meeting With NRC Project Management March 5, 1990 Location: One White Flint North, Conference Room #8811 Rockville, Maryland Tim *:

10 a.m. to 4 p.m.

Antada I.

Introduction

!!. General Topics and General Licensing Issues A. General Topics

1. Communications

2. Timeliness

3. Coordinatior, Between Four NU Units i.

4. Handling of Emergency Technical Specification / Enforcement Discretion l

S. Status of Forthcoming NRC Guidance on JCOs

6. Coordination With Resident Inspectors B. ISAP/IPE Including ISAP License Condition C. Exposure Reduction Initiatives D. Status of SEP Items E. Inspections by NRC III. Selected Plant-Specific Licensing Issues A. Implementation of EPG, Rev. 4. for Millstone 1 B. Degraded Grid Issue-Millstone 1 C. Reactor Building Component Cooling Water Issue--Millstone 2 D. Fire Protection Issues--CY, Millstone 2 E. Appendix J Exemptions--CY F. Status of TMI Action Items--Millstone 1, 2, 3, and CY I

i 2o o

G. Upcoming Issues

1. Containment Pressure Technical Specification Change-M111 stone 3

2. Core-Melt Frequency Reduction Initiative CY

3. New LOCA Analysis-Millstone 1, 3 and CY

4. Spent Fuel Pool Analysis Millstone 3

'!V.

NRC 0bservations and Feedback and Comments i

V.

Summary and Conclusions P

+

l

II.A.1 COMUNICATIONS 1

,AY-T0-DAY COMMUNICATION WITH PROJECT MANAGER D

o o

PERIODIC " FACE-T0-FACE" NEETINGS WITH PROJECT MANAGER o

GENERIC CORlUNICATIONS--GENERIC LETTERS, BULLETINS o

SIMS LIST i

l i

i II.A.2 IIMELINESS l

o AESPONSES TO SPECIFIC NRC REQUESTS ARE GENERALLY VERY TIMELY o

DISCUSS WAYS TO BETTER FACILITATE RESOLUTION OF i

LONG-STANDING ISSUES I

l i

e 0

1 l.

II A,3 COORDINATION BETWEEN FOUR NU UNITS o

. COORDINATION FOR FOUR DIFFERENT UNITS:

HADDAM NECK, MILLSTONE 1, MILLSTONE 2, AND MILLSTONE 3 o

ISSUES GENERIC ISSUES GENERIC TECH SPECS PROMPT INFORMATION REQUESTS TO INDIVIDUAL PMs o

NU PHILOSOPHY EXTRA EFFORTS TO MAINTAIN CONSISTENCY (PHILOSOPHY AND PRACTICD INTRODUCES SPECIAL CHALLENGES o

EXAMPLES TMI TECH SPECS SPDS CRDR ULTIMATE HEAT SINK 2

i i

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l II.A.4 HANDLING 0F EMERGENCY-i TECH SPEC / ENFORCEMENT DISCRETIONS i

l l

o MU EXPERIENCE IN HANDLING EMERGENCY TECH SPEC MILLSTONE 3 EXAMPLES MILLSTONE 2 EXAMPLES HADDAM NECK EXAMPLES

?

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POSITIVE NRC SUPPORT 9

MF t

1 1

l.

II.A.5' STATUS OF FORTHCOMING NRC GUIDANCE ON JCDs 1

o AlU'S EFFORT IN JC0 PROCESS JCOs PREPARED UNDER 10CFR50.49 FOR EQ PURPOSES; CONCEPT IS NOW EXTENDED INT 0 OTNER AREAS; EXAMPLES:

HADDAM NECK SERVICE WATER TEMPERATURE MILLSTONE 2 STEAM GENERATOR TUBE PLUGS i

MILLSTONE 1 SWITCNGEAR CABINET SEISHIC HOUNTING NU PRACTICE ON JCOs IS GENERALLY CONSISTENT WITN JAMES PARTLOW MEMORANDUM 0F AUGUST 9, 1989.

NU PROCEDURE 2.29 ON JCOs TO BE ISSUED BY APRIL 1, 1990; SCNEDULES FOR COMPLETING JCOs DO NOT IMPACT REPORTABILITY EVALUATIONS NU WORKING WITH BWROG COR4ITTEE ON JC0 GUIDANCE

II.A 6 C00RDINATION WITH RESIDENT INSPECTORS o

PRIMARY PATH 0F C0 H NICATION FOR GFL TO THE NRC IS THROUGH THE PMs (PRIMARY PATH 0F COMNICATION FOR THE SITE IS THE RIs) l o

THERE IS ALS0 REGULAR CO M NICATION WITH RESIDENT INSPECTORS INFORMAL:

DURING VISITS TO THE SITE / TELEPHONE AT DIFFERENT LEVELS:

BOTH SUPERVISOR / LICENSING LEADS SUPPORTIVE:

WE ATTEMPT TO PROVIDE SUPPORT, DOCUMENTATION, F0LLOW-UP~

o COORDINATE NUSCO INTERFACE k

o WE WORK TO ENSURE CONSISTENT COINUNICATIONS WITH BOTH THE PMs AND RIs i 1

II.B INTEGRATED SAFETY ASSESSMENT PROGRAM (ISAP)/

INDIVIDUAL PLANT EXAMINATIONS (IPE) y '.

o PENDING ISAP LICENSE CONDITION FOR MILLSTONE 1 AND HADDAM NECK o

ISAP UPDATE SUBMITTALS, INCLUDING. INTEGRATED IMPLEMENTATION SCHEDULES (IISs), EVERY 6 MONTHS o

HADDAM NECK PUBLIC SAFETY ATTRIBUTE MODEL CHANGES o

INITIAL MILLSTONE 3 ISAP METHODOLOGY SUBMITTAL IN SECOND QUARTER 1990 o

FIRST MILLSTONE 3 ISAP RANKINGS AND IIS SUBMITTAL IN FOURTH QUARTER 1990 o

MILLSTONE 2 ISAP EFFORTS WILL COM ENCE IN 1991 o

GENERIC LETTER 88-20 RESPONSE SUBMI1TED ON JULY 7 AND OCTOBER 31, 1989 o

ISAP IS FOUNDATION FOR IPE RESPONSE __

1 II.B INTEGRATED SAFETY ASSESSMENT PROGRAM (ISAP)/

i INDIVIDUAL PLANT EXAMINATIONS (IPE) (CONTINUED)

)

E o

GENERIC LETTER / BULLETIN RESPONSES BASED UPON ISAP PROCESS o

MILLSTONE 3 LEVEL 3 PRA COMPLETED

~

SlH4ARY REPORT SUBMITTAL SCHEDULED FOR MID-1990 l

o MILLSTONE 1 l

l LEVEL 1.PRA (FRONT-END ANALYSIS) COMPLETE BACK-END ANALYSIS IN PROGRESS SUINARY REPORT SUBMITTAL SCHEDULED FOR MID-TO LATE-1991 o

HADDAM NECK LEVEL 1 PRA (FRONT-END ANALYSIS) COMPLETE l

BACK-END ANALYSIS WILL ColMENCE UPON COMPLETION OF MILLSTONE 1 EFFORT SUPNARY REPORT SUBMITTAL SCHEDULED FOR MID-1992

-- A-I

II.B

. INTEGRATED SAFETY ASSESSMENT PROGRAM (ISAP)/

INDIVIDUAL PLANT EXAMINATIONS (IPD (CONUNUE.D) o MILLSTONE 2 LEVEL 1 PRA (FRONT-END ANALYSIS) IN PROGRESS BACK-END ANALYSIS WILL COMENCE UPON COMPLETION OF HADDAM NECK'S EFFORT SUMARY REPORT SUBNITTAL SCHEDULED FOR END OF 1992 TO EARLY 1993 1

r 9

II.C EXPOSURE REDUCTION INITIATIVES o

PURPOSE:

TO REDUCE OCCUPATIONAL EXPOSURE, TO INCREASE

' RAD WORKER EFFICIENCY WHILE PERFORMING THE INSPECTION OR REPAIR o

SHORT-TERM AND LONG-TERM ACTION INITIATIVES SHORT TERM INCREASE ALARA AWARENESS WORK PRACTICE REVIEW CONSTRUCTION WORK EFFICIENCY JOB CANCELLATION / SCOPE REDUCTION LONG TERM DECONTAMINATION IMPROVEMENTS STEAM GENERATOR INSPECTION / PLUGGING CRITERIA (HADDAM NECK ISAP TOPIC N0. 2.116)

PRIMARY CHEMISTRY CONTROLS l

STEAM GENERATOR REPLACEMENTS TECHNICAL SPECIFICATION IMPROVEMENTS 041LLSTONE 1 ISAP TOPIC NO. 2.119) o CANDIDATE TOPICS FOR MORE DETAILED DISCUSSION 1

11.0 STATUS OF SEP o

SEE ATTACNED MATRICES FOR HADDAM NECK AND MILLSTONE 1 o

STATUS SUMARY:

SOME ISSUES REMAIN OPEN, PENDING RESPONSE FROM NRC STAFF

'SOME ISSUES HAVE BEEN INCORPORATED INTO ISAP SOME ISSUES WILL BE RESOLVED WHEN THE NEW TECN SPECS ARE ISSUED FOR HADDAM NECK

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nellstone unit me. 1 SEP STATUS l

5EP Topic No.

Depertment\\porsen l

(IsAP as.)

Title States Comments aesponsitple Cleesee Seeament III-F.s aestos tedes, sess,e Closed

n. t. earle w eer to l

(I.lg)

Criteria, toed Combles-E. J. arec e s. deced Jossary 4 tiens and enacter Caetty 3989 Bestge Criteria j

j III-8.A Loose-Parts Moniterles Closed Isose detened more 3. Igor.

f 1

and Core terrel Vitratien

]

gesetterleg i

i III-)G.A Thereal-Geerload Protec-Closed SER from MC tien for notors of noter-Soyeester 36. 1985. 375AR Gyarated valves Supplement Sectlen 2.13.

l IV-2 Reactivity Centrol Closed Asen h eet #97 to t kenee.

f i

Systems I

I V-5 Reacter Caelant Pressere Closed asundesat #gF to t kones.

l l

Soundary Leekage Detectles i

t l

V-6 Reacter Wessel Integrity Closed

9. n Creedfte.ld letter to f

- li. u.est m.

r.

V-19.A Restdoel Neet Removal Closed IP5M. Sectles 3.1.

i system leset Enchaager Tube Fallere i

V-10.8 Restdoel Itset Demoval Closed 3PSAR Supplement Settlen 4.

j system Bellat>Ility I

i I

1 i

A 4

I.

I 4

Isore to 1999 Page 4 of T t

Wl11stene unit see. I SEP STATUS j

=

SEP r

Tepic Iso.

SepartmentVWoon (Isar me.)

Title States Casseets AessenstM e Closure h 1

I V-II.A Aegelrenoots for Closed treft NIBOS, ested April 2 j

(I.M)

Isoletten of sligh-and 39BF.

low-Pressere Systems i

T-II.8 WR System Interlock Closed IPEM, Sectfen 3.1 i

Regelrements I

i i

T-12.A tieter Cheatstry tief ts Closef Assadeest 899 to L9teese.

I I

VI-I tryonic Meterials and Closed J. Shoe to W. C. Counsl1 fest Acc6 dent Cheelstry febreery N, 1982.

l l

VI.4 Centalosset Isolatten C1esed Sta free the Staff en July 7, (I.03) 8983.

VI-F.e.3 ECC5 Acteetten System Closed SER free the Staff ested July 5, 1983.

j VI-7.A.4 Core Spray Norrie Closed IP5M 3ectlen 4.22.

I Effectleeness VI-7.C.:

sedendent enstte fosse spee A=stles met cleswe. (lac see me)

Isar sahatttel dated Rosester 9, (1.21) systems 19es.

i 5

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we

-e

-- c w---w-ev--<wa w--

&-=s

-e 4vw+-

e----r-<----we4--,

v-a*

-+-g--w-

--we-ww,%---

---,.--e,ww-+,,-e--

+,.-.w-

_e---.

,.----e--

-w--

8m m A 20 1988 Pawe 5 of y flillsteme Welt No.1 SEP $1A 11 SEP Department' h Topic no.

Comments aespuestble Cleomre h (ISAP IIo.)

Title Lsates IPEIR Sgplement, Sectten 4.'

VI-IS.A Testleg of RTS and E5F Closed (I.22)

VII-I.A Isoletten Seeltes W

Amelting SER from the staff.

Setenen teacter Protectlen System (mPS) and steelterlag Systems VII-3 Systems Regelred for Closed JPSM Secties 4.2.6.

Safe *Mh VIII.I.A Potential Egelpment W

Werk was ceapleted darlag 1999 SEE June 30, 3 M.

(I.25)

Falleres Asseclated Befsellag Ostage (TAC M8297).

with Begraded Grid Preposed clesley le Septeater 29 Voltage 1989 ISAP Aeport.

VIII.2 Onsite Emergency Power W

Amelting cleeure by IIRC (TAC M9307).

SER from IK, deced Augost N, 19es, tsar esamettel deted (I.22)

Systems September 29, 3959.

VIII-3.A Statten Osttery Test Closed Amendment sgs to ticense.

Segstrousets VIII-3.8 9.C. Peuer Systee 8es W

Work completed durlag 198g SEE from IMC Jammery 7.

(1.25)

Voltage stentterlag and Refseling Detage. (TAC M6207) 1995 closed port of this Annunciatten; Proposed cleslag in Septeu6er 29 top 6c.

l Battery States Alares and 1989 ISAP Aeport.

l Indicatless e

n = m r. m e Pese o of 7 i

Nillstone Unit k. I t

SEP STATUS l

r t

SEP Topic IIo.

Department \\hrsee (ISAP IIe.;

Title States Ceements ResponslH e Closers Becesent 4

i II-3 Statten Service and Closed BP5fR Sectie's 4.31.

t Coelleg Isoter Systems l

)

II-5 Westilattee Systems Closed SER free the Staff en (1.95)

Septester 34, 1932.

IV-1 Decrease la Feedsater Closed SEE free K i

i Temperature. Increase le Flee, Increase in Steam Setember 3), 3933.

(

Flee, and leadvertent Opeeleg of a 5teae Generator Selief er I

Safety Velve.

XV-3 tess of Esternal lead Closed IF58R Settlen 4.34.

Torblee Trip, less of i

Condenser Wacuum, l

Closure of IInta Steaa Isolatlee Valve { Blat),

and Steam Pressere 1

Regulater Falleres j

(Closed) i XV-T Reacter Ceolant Pump Closed B. W. Crutchtleid to l

i Reter Selaere and Shaft Break

u. G. Ceumsti. Decesher 4, 1983. IP5AR, Settlen 3.1 i

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.--aw

.-,.,,,+-w-

~-----e..

-.p.

.,nm.-,e-,

-.*,e m-,,

,-,...-n.,

- -.. - -. +,.. _ _ -... - -

-,a-

Stord 1. '999

'i 1

hpfd1 pHilstone Unit Ite. I SEF STATUS SEP Tepic IIe.

Deporteestversee (IsaPas.)

iltle States Commisets aespenstble Closure Seemosmt i

N-lo nesteleyscal C m _ - Closed ammmmet see to liessee ces of Fallere of Small and MC MR June 21. Iges.

t Lines Carrytes *rleary Coolant Getstee Contalement.

N-IS ~

Radleleylcal Conseguen-Cleoed W SUB to Itcense and l

4 ces of a Itale Steam Lise Inc SER June 23, ages.

l Ta11ere setside Contalement.

W-19 LOCAs Rosettleg From Clemed IP5m. Settlen 3.3.

.i 3pectrise of Postulated i

Pipe Greeks Within IICPS t

M:

I Total % SEP Tepics II AueItlag INIC closare le Open Tepics Scheduled ;e ISAP/il5 1

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II.E M cTIONS BY NRC e

i

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._4 U

9 i

RECFNr a UpcoMINc Mac MErnNcs '

Fehmay 10 l.

Enforcement Conference Shipment of Contaminated Materials i

Fehma? 2 Millstone Unit No. 2 Steam Generators 2

i l

Fehma? 12 CY Event V i

Fehman 26 2a Atomic Energy Control Board of Canada (visit coordinated through the NRC) l I

I Fehmaw 2R de NRC / NUMARC Maintenance Meeting I

Marth 1 l

\\

i j

March 1 Millstone Unit No.1 EOPs 1i l

I M arch Two day Pre SALP Meetings for Millstone. one per unit l

March 5 Counterpa.rts Meeting I'

March 12 CY Action Plan for Re-start, and Fitness for Duty March 22 Nuclear Safety Concerns Program i

I March / Aprli NU Reporting Philosophies and Processes April / May Mid Cycle SALP Meeting for thiM111 stone Site i

fune 4.a Haddam Neck Plant Requalification Program Evaluation Im is. 22 Millstone Unit No. 2 Requalification Program Evaluation f

l t

(19)

~ - ' - - - - ' ' - ' - " ~ " " - ' ' "

' ' ~ ~ ' '

i l

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III.B DEGRADED Git!D ISSUE o

INTENT OF 10CFR50 APPENDIX A, GDC 17 MET TO EXTENT PRACTICAL FOR HILLSTONE UNIT 1 o

INTENT 0F BTP PSB-1 ALSO MET o

COR41THENTS MADE IN 1980 AND REITERATED IN 1987 MET DURING 1989 REFUELING OUTAGE RELOCATE DEGRADED VOLTAGE TRIPPING LOGIC TO CLASS 1E BUSES INCORPORATE AN AUTOMATIC REINSTATENENT OF LOAD SNED CAPABILITY o

LONG NISTORY ASSOCIATED WITN ISSUES o

LICENSING BASIS vs. CURRENT CRITERIA 1

III C REACTOR BUILDING C0W ONENT COOLING WATER ISSUE i

i l

o DISCUSS POTENTIAL RESOLUTION 0F ISSUE l

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III.D FIRE PROTECTION ISSUES ONG0ING ISSUES o

HADDAM NECK NEW SWITCHGEAR BUILDING / APPENDIX R SCHEDULAR EXEMPTION PENDING FIRE PROTECTION EXBtPTIONS REQUEST FOR ADDITIONAL INFORMATION o

MILLSTONE 2 SER ON SAFE SHUTDOWN SYSTEM AVAILABILITY FIRE PROTECTION IMPROVEMENTS o

HADDAM NECK, MILLSTONE 1 AND 2 PENETRATION SEAL PROGRAM UPGRADE o

HADDAM NECK CABLE VAULT C02 SYSTEM UPGRADE

III.E 10 CFR 50. APPENDIX J o

.N0 PENDING EXEMPTIONS FOR MILLSTONE 2 Ale 3 o

HILLSTONE 1 EXEMPTIONS SUBMITTED IN APRIL 1988 o

HADDAM NECK EXEMPTIONS STATUS SCHEDULAR EXEMPTION STATUS OF H0DIFICATIONS REQUEST FOR EXEMPTIONS ISAP TOPIC No. 1.03

~

PREVIOUS DISCUSSIONS WITH NRC STAFF STATUS OF BESOLUTION l _.... _......

• 9 9

III.F IMI ACTIO!( ITDtS--0 PEN _ ITEMS ACTION BY STATUS HADDAM NECK I.D.1 CONTROL R00H DESIGN NU OPEN REVIEW II.B.1.3 RCS VENTS--PROCEDURES CLOSED II.F.1.2.F ACCIDENT HDNITORING--

CLOSED HYDR 0 GEN CONTROL-II.K.3.12.B ANTICIPATORY TRIP DN NRC OPEN TURBINE TRIP INSTALL H00 II.K.3.25.A POWER ON RCP SEALS NU OPEN PROPOSED N00 III.D.3.4.1 CONTROL ROON HABITABILITY NU OPEN GL 83-37 TECH SPEC CLOSED GL 85-12 RCP TRIP NRC OPEN MILLSTONE 1 I.D.1.2 DETAILED CRDR HU OPEN GL 83-26 &

TECH SPEC CHANGES NRC OPEN GL 83-37 1 1

III.F 1MI ACTION ITDtS--OPEN ITDtS (CONTINUED)

ACTION BY STATUS MILLSTONE 2 II.F.2.4 INSTRLMENTATION FOR ICC CLOSED INSTALLATION I.D.1.2 DETAILED CRDR NU OPEN MILLSTONE 3 I.D.2.3 SPDS FULLY IMPLEMENTED CLOSED e

a. s -

III.G.1 Mill (TONE 3 CONTAIMENT W11DREl)ESIGN o

PURPOSE o

BASES FOR THE PROPOSED DESIGN o

EXISTING PLANT DESIGN o

PROPOSED PLANT DESIGN LOCA REANALYSIS RADIOLOGICAL CONSEQUENCES CONTAIMENT INTEGRITY EQUIPMENT REVIEWS TECH SPEC CHANGES i

III.G.2 HADDAM MECK RISK REDUCTION o

PURPOSE:

TAKE A PR0 ACTIVE STANCE T0 REDUCE HADDAM j

. NECK'S C0RE-MELT FREQUENCY AND OVERALL RISK TO ACHIEVE i

COMPLIANCE WITH NE0 POLICY STATEMENT 19 o

TASK FORCE FORMED IN OCTOBER 1989 FROM PLANT STAFF AND VARIOUS ENGINEERING DISCIPLINES i

l o

TO DATE, HAVE HAD MANY MEETINGS AND VISITED YANKEE R0WE T0:

DEFINE SCOPE OF EFFORT IDENTIFY OTHER ISSUES TO ADDRESS IDENTIFY N005 TO RESOLVE TORNADO PROTECTION ISSUE i

1 REVIEW PRA FOR INSIGHTS RESULTS TO BE EVALUATED IN ISAP i

o STATUS i

L EFFORTS HAVE CONCLUDED THAT COMPLIANCE WITH SAFETY G0AL MAY BE ACHIEVABLE WITH VARIOUS PLANT J

IMPROVEMENTS, NO ONE MODIFICATION WILL DO IT ALL i

l TORNAD0 MODS SHOULD BE INDEPEWENT, IF POSSIBLE, l

FROM EXISTING PLANT EQUIPMENT KEEP DESIGN FOR ALL M0DS SIMPLE l ;

e III.G.2 MADDAN NECK RISK REDUCTION (CONTINUED) o

, CONCEPTUAL TORNADO PROTECTION MODS NEW AIR-COOLED DIESEL GENERATOR POS$1BLE NEW CHARGING PUMP I

POSSIBLE NEW AFW PUMP o

OTHER CONCEPTUAL N005 ADDITIONAL ATNOSPHERIC DUMP VALVES FOR COLD

{

SNUTDOWN NEW NONSAFETY CRADE CONDENSATE STORAGE TANK

'/

4 MAKEUP FACILITY FOR DWST

)

i PRESSURE INTERLOCK FOR LPSI/ CORE DELUGE H0Vs i

i REPLACE RNR SUCTION MANUAL BYPASS VALVE FROM CONTAINHENT SUMP WITH MOV f

FURTHER ELECTRICAL SEPARATION ON MCC-5 i

MAIN LUBE OIL PUMP FOR B ELECTRICAL DIVISION CHARGING PUMP f

i PORY BLOCK VALVE

/

ADDITIONAL MOVs TO SUPPORT LOCA RECIRCULATION USING CHARGING SYSTEM i

i

i I

HADDAM NECK CORE-MELT FREQUENCY l

I i

CURRENT CYCLE 16

, ISSUE FETIMATE ESTIMATE G0AL j

INTERNAL EVENTS 3,25 x 10-4 2.0 x 10-4 4.9 x 10-5 FIRES 4.5 x 10-4 8.5 x 10-5 1

x 10-5 l

i INTERNAL FLOODS 1.7 x 10-5 1.7 x 10-5 1

x 10-5

{

EXTERNAL FLOODS

?

7 1

x 10-5 SEISHIC 7

7 1

x 10-5 l

)

TORNADO 7

7.6 x 10-5 1

x 10-5

~l l

l HISCELLANEOUS 7.6 x 10-5 7

1 x 10-6 i

8.7 x 10-4 4

x 10-4 1

x 10-4 I

i 1

I i

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f l:

NU'1 NUCLEAR PLANT CORE-MELT FREQUENCY DATA i

CY BP.1 lEl HPl l

l l

I.

INDIVIDUAL RISK

?

?

?

MEETS l

5AFETY GOAL CORPORATE G0AL:

j

. MORTALITY RISK i

• TO MAXIMUM j

VIDUAL<10"[/YR t

i EXPOSED INO -

l POPULATION RISK

?

?

?

MEETS l

SAFETY G0AL l

CORPORATE G0AL:

STATISTICALLY ESTIMATED POPU-LATION RISK

<1 DEATH /

1000 MWs/YR l

III. LARGE SCALE FUEL' MELT SAFETY GOALS

}

INTERNAL EVENTS 3,25 E-4/YR 5.31 E-5/YR 7

6.3 E-5/YR FIRES 4.52 E-4/YR 2.58 E-5/YR

?

4.5 E-6/YR l

l INTERNAL FLOODS 1.7 E-5/YR 2.5 E-7/YR

?

NEGLIGIBLE

[

t EXTERNAL FLOOD 5

?

?

?

NEGLIGIBLE i

SEISMIC

?

?

?

9.1 E-6/YR i

l MISCELLANEOUS 7.6 E-5/YR*

?

?

NEGLIGIBLE I

TOTAL 4.7 E-4/YR**

7.92 E-5/YR

?

7.7 E-5/YR

/

CORPi.4 ATE 40AL:

TOTAL CORE MELT FRE0 ENCY

<10'g/YR l

i cHIGH WINDS / TORNADO coESTIMATED TO DECREASE BY ABOUT HALF FOLLOWING THE CURRENT REFUELING OUTAGE

l III.G.3 NEW LOCA ANALYSIS--MILLSTONE 1 Alm 3 l

Als HADDAM NECK I

MILL 5ITONE3 l

l o

CYCLE 4--VANTAGE 5H FilEL (17 x 17 FUEL ASSEMBLIES) l

\\

l 0

NEW LOCA AND NON-LOCA ANALYSIS l

o LOCA l

LARGE-BREAK--BASN CODE l

SMALL-BREAK--NOTRUMP CODE

?

o ALSO ANALYSIS FOR N-1 LOOP j

-l HADDAM NECK PLANT l

o 05/88 PRESENTED PLANS FOR ZIRC CONVERSION AND DEVELOPMENT OF IN-H0USE LARGE-BREAK LOCA l

CAPABILITY (SUPPORT CYCLE 12) l o

12/88 SUBMITTED AMENDMENT TO SMALL-BREAK LOCA TOPICAL l

o 01/89

$UBNITTED NULAP5-LB TOPICAL REPORT l

l o

02/89 SUBMITTED NUFRAP-T6 TOPICAL REPORT o

08/89 NU/CY MEETING WITH NRC; PRESENT PLAN FOR l

l USING hlCOBRA/ TRAC FOR LARGE-BREAK LOCA i

1 o

10/90 WCAP TO BE SUBMITTED FOR COMPLETED ANALYSES i

i l

f

]

l '

c

1 l

III.G.3 NEW LOCA ANALYSIS--MILI(T0NE 1 AND 3 AND HADDAM NECK 1

o COMPLETE REANALYSIS PERFORMED 9/89 (NEDC-31740P) i SU R RY OF CHANGES FULL CORE DRILLING CREDITED IN REANALYSIS; LARGE PCT BENEFIT

^

REDUCED ECCS ASSUMED FLOW RATES AND SHUT 0FF HEADS; SMALL PCT PENALTY ASSUMED LPCI MINIMUM FLOW BYPASS VALVES LOCKED OPEN; NO PCT PENALTY l

MAXIMUM ALLOWED PCT SET AT 21700F vs. 2200 F I

0 REG. LIMIT RESULTS l

i SINGLE FAILURE AND LIMITING BREAKS UNAFFECTED MAPLHGR CURVES HIGHER FOR NEW ANALYSIS vs.

0LD; r.r., MAXIMUM ALLOWED xW/Fr HIGHER; i

RESULTS IN MORE THERMAL LIMIT MARGIN' L

l i

4

...--L.--

s..

III.G.3 HDLLQCA ANALYSIS--MILLSTONE 1 AND 3 i

AND HADDAM NECK o

TECHNICALSPECIFICATIONCHANGES REWRITE SECTION 3.5 (CORE AND CONTAINMENT C0OLING i

SYSTEMS) 0F TECH SPECS AND ASSOCIATED BASES SECTION REWRITE RELATED SECTIONS OF TECH SPECS TO.BE CONSISTENT WITH HEW 3.5 AND CLARIFY REQUIREMENTS-(PARTICULARLY ELECTRICAL AND' REFUEL REQUIREMENTS) 3.7--CONTAINMENT SYSTEMS (PARTIAL REWRITE) 3.9--AUXILIARY ELECTRICAL SYSTEM (COMPLETE

.l REWRITE) 3.10--REFUELING (COMPLETE REWRITE) o COMPLETE REWRITE OF UFSAR SECTION 6.3 ECCS o

TINAL GOAL UFSAR, TECH SPEC, BASES AND ISI PROGRAM ALL CONSISTENT AND UP TO DATE o

TIME FRAME l

MAY-JUNE 1990 SUBMITTAL f

NEED APPROVAL BEFORE CYCLE 14 START-UP (MARCH 1991)

L r

t I

i III.G 4 SPENT FUEL P0OL ANALYSIS

?

l MILLSTONE 3 i

o CYCLE-SPECIFIC ANALYSIS i

o P0TENTIAL PIPING SUPPORT N0DIFICATIONS 1

1 i

o H0LTEC ANALYSIS HOLTEC EXPERIMENT MARGIN FOR PLUGGED HEAT EXCHANGER TUBES i

I i

o j

l L q

-...._m_,

r I

SUM RRY AND CONCLUSIONS o

48RC FEEDBACK AND OBSERVATIONS i

i o

RITURE NEETINGS7 FREQUENCY PARTICIPANTS 4

e i

J l

l i

l.

_ _ _ - - - - - - - - -