ML20029A229
| ML20029A229 | |
| Person / Time | |
|---|---|
| Site: | Haddam Neck, Millstone File:Connecticut Yankee Atomic Power Co icon.png |
| Issue date: | 01/28/1991 |
| From: | Jaffe D Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 9102050096 | |
| Download: ML20029A229 (95) | |
Text
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!,'f usey[c UNITE D sT ATEs
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s January 28, 1991 Docket Nos.: 50-213, 50-245 50-336 and 50423 LICENSEE:
hortheast Utilities FACILITIES:
Haddam Neck and Millstone Units 1, 2 and 3
SUBJECT:
DISCUS $10N OF LICENSING ISSUES OF GENERAL INTEREST On Thursday (NU) met at NU's Corporate Headquarters at 107 Seldon Street,, Novenb Utilities Berlin, Connecticut. A list of attendees is contained in Enclosure 1.
The meeting was the third in a series of meetings being held for the purpose of discussing topics of interest associated with NU's licensed facilities. An outline of the topics discussed at the meeting is contained in Enclosure 2.
The NRC staff and NU had previously discussed the subject of NU's proposed ALARA present6 tion.
It was suggested that NU present the details of their program as part of a major initiative such as the upcoming Millstone Unit 2 Steam Generator replacement.
With regard to ISAP, the NRC noted that the Millstone Unit 3 program appeared to be underway in that ISAP was referenced in the recent COPPS submittal.
NU indicated that the Millstone Unit 2 ISAP framework would be conolete in approximately one year. The NRC staff and NU discussed the ISA) grogramwith regard to the level at which an ISAP safety improvement could be dropped."
The NRC staff indicated that no generic limit should be established and that each safety 1ssue should be considered on a case-by-case basis. The NRC staff and NU discussed the relationship between ISAP and the Regulations (e.g.,)while Station Blackout is part of ISAP, it is also addressed by the Regulations.
NU inquired as to the details of the IRRIS program.
The NRC-staff indicated th6t IRRIS was still in its formative stage and discussions on this topic should be deferred.
The NRC staff and NU discussed the issue of " operability" hat, for safetyas it applies to Technical Specifications (TS).
The NRC staff indicated t systems required to be operable by the TS, if a component of the sy(e.g.,becomes stem inoperable but is still capable of performing its safety function loss of environnental or seismic qualifications, low flow, etc.), the issue can be addressed in a JC0 unless the TS specifically requires entry into an Action Statement.
The NRC staff and NU discussed the topic of non-ASME Code repairs. The NRC staff reiterated its position that every non-ASME Code repair requires relief from the ASME Code.
Stop-gap leakage reduction measures may be undertaken in the interim, until receipt of code reliet, but these measures should be non-destructive.
9102050096 910128 hDR ADOCK 05000213 d
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Northeast. Utilities
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The NRC-staff and NU discussed the upcoming improvements to the Millstone Unit 1 TechnicalSpecifications(TS).
NU indicated that, if Phase I was completed in 1991 they would be satisfied; however, those changes to the TS which are required on a more expeditious basis will be identified.
During the meeting several action items were identified for further consideration as f 110ws:
Millstone Unit 1:
NU should prepare its IPE conclusions regarding.
The hardened vent issue. The NRC staff and NU should discuss the combustible gas control issue. The issue of control room habitability requires NRC staff follow.up (as does this issue for Haddam Neck).
Future TS changes for Phase I should be discussed with regard to scheduling; NU will advise the staff on which issues cannot wait for completion of Phase 1.
- - Millstone __ Unit 2:
The NRC and NU should discuss the JC0 for the
- auxiliary steam system.
A' schedule for a full presentation of NU's Steam Generator replacement program should be established.
- Haddam Neck: The.NRC staff should establish a. review schedule for issues related to the fuel conversion.
- General: The NRC staff should provide comments to NU concerning the impact of the proposed changes to 10 CFR Part 20. The NRC staff will provide comments on-the "no significant hazard consideration" process.
The NRC will schedule the next NU/NRC staff meeting in approximately.six months.
r David H. Jaffe, Project Manager Project Directorate I.4 Division of Reactor Projects. I/II Office of Nuclear Reactor Regulation
Enclosures:
1.
List of Attendees 2.
Outline cc w/ enclosures:
See next page DOCUMENT NAME: LICENSING ISSUE
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Mr. Edward J. Mroczka Haddam Neck & Millstone Nuclear Power Northeast Nuclear Energy Company Station Unit Nos. 1, 2 & 3 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 1 Department of Environmental Protection U. S. Nuclear Regulatory Commission State Office Building 475 Allendale Road Hartford, Connecticut 06106 King of Prussia, Pennsylvania 19406 Bradford S. Chase, Under Secretary First Selectmen Energy Division Town of Waterford 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. Raynond, Resident Inspector Millstone Nuclear Power Station Millstone Nuclear Power Station Northeast Nuclear Energy Company c/o U. S. Nuclear Regulatory Commission Post Office Box 128 Post Office Box 811 Waterford, Connecticut 06385 Niantic, Connecticut 063S7 C. H. Clement, Nuclear Unit Director M. R. Scully, Executive Director Millstone Unit No. 3 Connecticut Municipal Electric Northeast Nuclear Energy Company Energy Cooperative 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 Municipal Wholesale Room 8608C Electric Company Washington, D.C.
20426 Post Office Box 426 Ludlow, Massachusetts 01056 Burlington Electric Department c/o Robert E. Fletcher, Esq.
271 South Union Street Burlington, Vermont 05402 l
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2 Mr. Edward J. Mroczka Haddam Neck & Millstone Nuclear Power Northeast Nuclear Energy Company Station Unit Nos.1, 2 & 3 H. F. Haynes, 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 063B5 Waterford, Connecticut 06385 Charles Brinkman, Manager Board of Selectnen Washington Nuclear Operations Town Hall C-E Power Systems Haddam, Connecticut 06103 Combustion Engineering, Inc.
12300 Twinbook Pkwy J. T. Shediosky, Resident Inspector Suite 330 Haddam Neck Plant Rockville, Maryland 20852 c/o U. S. Nuclear Regulatory Commission Post Office Box 116 East Haddam Post Office J. P. Stetz, Nuclear Station Director East Haddam, Connecticut 06423 Haddam Neck Plant Connecticut Yankee Atomic Power Company RFD 1, Post Office Box 127E East Hampton, Connecticut 06424 G. H. Bouchard, Nuclear Unit Director Haddam Neck Plant Connecticut Yankee Atomic Power Company RFD 1, Post Office Box 127E East Hdmpton, Connecticut 06424 E
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ENCLOSURE 1 LIST OF ATTENDEES NRC Northeast Utilities M. Boyle P. Blasioli P. Habishorst D. Hitchcock D. Jaffe W. Hutchins W. Raymond R. Kacich J. Shedlosky R. Joshi J. Stolz P. Miner G. Vissing R. Necci A. Wang S. Oats D. Haverkamp S. Orefice E. Perkins J. Resetar J. Stetz S. Scace G. vanNoordennen K. Zita
Northeast Utilities January 28, 1991 Di_stribution:
Docket-Files,i NRC & Local FDf:s F. Miraglia J. Partlow SVarge EGGreenman PD I-4 File JStolz DJtffe OGC EJordan ACRS (10)
JCaldwell MBoyle PHabishorst JShedlosky GVissing AWang DHaverkamp
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ENCLOSURE 2 d
i NRC/NU COUNTERPARTS MEETING NOVEMBER 8, 1990 e
e
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NRC/NU Counterparts Meeting ' '
November 8, 1990 Location:
Conference Dining Room (C1S2)
Time:
10 a.m. to 4 p.m.
Aaenda I.
INTRODUCTION II.
ITEMS IDENTIFIED IN PREVIOUS MEETINGS III. GENERAL LICENSING TOPICS A. Status-of USI, TMI Items, SEP Items, GSI B. Plant-Specific Regulatory Issues C. NU/NRC Interface on Selected Topics
- 1. Use of Industry /NRC-Sponsored Technical Specifica-tion Improvement Initiatives--e.g., Core Altera-tion Definition, Seismic Technical Specification
- 2. Neutron Flux Monitoring System for BWRs
- 4. Use of GL 90-05, " Guidance for Performing Tempor-ary Non-Code Repairs of ASME Code 1, 2 and 3 Piping," Position on NU Plants IV.
OTHER REGULATORY INTERFACE ISSUES A. License Amendment Format and Content B. SALP Process Changes C. Midcycle SALP D. Emergency, Exigency, and Temporary Waivers E. Operability V.
SELECTED NU INITIATIVES A. Millstone 2 Steam Generator Replacement Project i
B. Millstone 1 Future Technical Specification Changes VI.
SUMMARY
AND CONCLUSIONS Page 1
,a NRC/NU Counterparts Meeting November 8, 1990
- 1. INTRODUCTION Page 2
NRC/NU Counterparts Meeting November 8, 1990 II. ITEMS IDENTIFIED IN PREVIOUS HEETINGS Page 3
NRC/NU Counterparts Meeting November 8, 1990 II.
ITEMS IDENTIFIED IN PREVIOUS MEETINGS lifLC 1.
Additional Guidance Regarding Seismic Restraints (GL79-14, Supplement 2) 2.
Extended Fuel Cycles 3.
ALARA Initiatives Page 4
~
NRC/NU. Counterparts Meeting November 8, 1990 II.
ITEMS IDENTIFIED IN PREVIOUS MEETINGS (Cont.)
HM Action Item Comoleted Items Recentiv Submitted Response to Staff Questions on CRDR--
Submitted on Millstone 1 06/29/90 Plant-Specific Simulator Certification Submitted on Submittal for Millstone 1 07/03/90 Steam Generator Shutdown Submittal--
Submitted on Hillstone 2 07/03/90 Control Room Emergency Ventilation / Alternate Submitted on Power Supply Technical Specifications for 07/13/90 Millstone 2 Generic. Letter 88-11--M111 stone 1, 2, 3 and Submitted on Haddam Neck Plant 07/18/90 Response to NRC Degraded Grid Letter--
Submitted on Millstone 1 07/20/90 Spent Fuel Pool Requirements Technical Submitted on Specifications--504 Hours--Millstone 2 08/07/90 Containment Hardened Vent Issue--Millstone 1 Submitted on 08/08/90 and 09/04/90 Generic Letter 87-09--Technical Submitted on Specifications--Millstone 2 08/09/90 Generic Letter 89-14--Technical Submitted on Specifications-(Removal of 3,25 Limit) for 08/22/90 for Millstone 1 and 2
- MP1, 11/08/90 for MP2 Millstone 3 IPE Summary Report Submitted on 08/31/90 t
Page 5
NRC/NU Counterparts Meeting November 8, 1990 II.
ITEMS IDENTIFIED IN PREVIOUS MEETINGS (Cont.)
HM Action Item Comoleted Items Recentiv Submitted (cont.)
Detailed CRDR Schedule--Haddam Neck Submitted on 09/28/90 Zircaloy Clad Conversion / Appendix K Submitted on Exemption Request--Haddam Neck 09/26/90 RHR Autoclosure Interlock Deletion Technical Submitted on Specification--Millstone 3 10/25/90 Cycle 4 Reload Submittal--Millstone 3 Submitted on 11/01/90 Revision of IST Program--Millstone 1 Submitted on 11/05/90 Response to Generic Letter 90-05 on Non-ASME Submitted on Code Repairs--Millstone 1, 2, and 3 and 11/05/90 Haddam Neck 1
d Page 6
NRC/NU Counterparts Meeting November 8, 1990 II.
ITEMS IDENTIFIED IN PREVIOUS MEETINGS (Cont.)
EU Action Item Taraet Date Vocomina Initiatives ISAP License Condition for Millstone 1 and Awaiting Haddam Neck Staff Input to Arrange a Meeting Nozzle Safe-End Weld Inspection Requirements--
Cancelled Millstone 1 RCP Seal Leakage Submittal--Haddam Neck 11/15/90 MCPR Safety Limit Technical Specification 11/16/90 Change--Millstone 1 Initial Millstone 3 ISAP Submittal 11/16/90 Appendix A GDC Review of Containment 11/30/90 Penetrations--Haddam Neck Fire Protection / Spray / Sprinkler /Halon 11/30/90 Technical Specifications--Millstone 2 Enclosure Building Filtration System Tech-11/30/90 nical Specification for Millstore 2 LOCA Analysis--Haddam Neck Plant--So
't 11/30/90 WCAP Millstone 3 ISAP Rankings and IIS Submittal 01/31/91
' Millstone 1 1PE Submittal 09/30/91 Haddam Neck IPE Submittal 07/30/92 Millstone 2 IPE Submittal 03/30/93 Page 7
p-NRC/NU Counterparts Meeting November 8, 1990 III, GENERAL LICENSING TOPICS 4
i l
Page 8 i
,~.
NRC/NU Counterparts Meeting November 8, 1990 III.A St?.tus of USI, TMI Items, SEP Items, GSI
- ?;
f0i d
v' Page 9
g.
,0 '
NRC/NU Counterparts Meeting.
November 8, 1990 III.A Status of USI. TMI Items. SEP items. GSI Unresolved Safety' Issues (USI)--00en Items Had_ dam Neck Plant Action 111 1 Titie
._By_
Remar A-31 RHR Shutdown NU Issue addressed Requi remer.t under ISAP Topic 1.02.
A-40 Seismic Design NU Issue addressed Criteria under ISAP Topic 1.04; to be com-pleted by 6/92.
A-44 Station Blackout NRC Licensee response.
under Staff-review.
A-46 Seismic Qualifi-N'J Being' pursued via cation of Equip-SQUG methodology.
ment ~in Operat-Addressed-under ISAP ing Plants Topic 1.48.
Work currently scheduled to commence 6/92.
A-47 Safety Implica-NRC Licensee response tions of Control under Staff review.
Systems-
-Millstone Unit 1 Action l!11 Title By Remarks A-1 Water Hammer NU Although no A-1 actions were=
required for Millstone 1, NNECO L
is evaluating A-1 as part of ISAP Topic 1.43.
Page 10 l-y
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NRC/NU' Counterparts Meeting November 8, 1990 III.A Status of USI. TMI Items. SEP Items GSI (cont.)
Unresolved Safety Issues-(USI)--Doen Items (cont.)
Millstone Unit 1 (cont.)
Action MS T, Title By Remarks A-40 Seismic Design NU Being addressed as Criteria part of ISAP Topic 1.06.
A-44 Station Blackout NRC NRC-issued SER.
Implementation by 1993 refueling outage, pending NRC acceptance of schedule.
A-46 Seismic Qualifi-NU Being pursued via cation of Equip-SQUG methodology; ment in Operat-work currently ing Plants scheduled to com-mence 1/93.
A-47 Safety Implica-NRC Licensee response tions of Control under Staff review.
Systems A-48 Hydrogen Control NRC Licensee position under Staff review.
Millstone 2 Action M11 Title By Remarks A-44 Station Blackout NRC NRC-issued SER.
Implementation by 1993 refueling L
_ outage, pending NRC L
acceptance of schedule.
L Page 11 l-ee1 m
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w
NRC/NU Counterparts Meeting November 8, 1990 III.A' Status of USI. TMI-Items. SEP Items. GSI (cont.)
Unresolved Safety Issues (USI)--00en Items (cont.)
'Mi-listone 2 (cont.)
Action-Ull Title By Remarks A Sei smi c-Quali fi-NU Being pursued via cation of Equip-SQUG methodology; ment in Operat-work currently ing Plants scheduled to com-mence 7/93, A-47 Safety Implica-NRC Licensee response tion of Control under Staff review.
Systems Millstone 3 Action MSI Title By Remarks A Station Blackout-NU NRC-issued SER implementation by 11/92.
A-47 Safety.Impli'ca-NRC
. Licensee response tions of Control under Staff review, Systems r
Page 12
. _ =
l ru
.NRC/NU Counterparts Meeting November 8, 1990-III.A Status:of USI. TMI-Items SEP Items.'GSI1(cont.)
~
TMI Action Items--Ocen Items Action Bv Status Haddam Neck I.D.1 Control Room Design NU Open Review II,N 3.25.A.
-Power on RCP Seals NU Open i
Proposed Mod III.D.3.4.-1 Control Room Habit-NRC Open ability Millstone 1 I.D.1.2
-Detailed CRDR NU Open GL183-36 &-
Teci-Spec ~ Changes NRC Open-GL-83 '-
-Millstone 2:
1.D.1.2-Detailed CRDR NU Open Millstone-3 None Page 13 n
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1 I
race 1 ColetECTICUT TAI 4 TEE SEP STATUS WFBRTES: 2/1/T9 SEP TOPIC ISAP TOPIC DEPARTMDtT/FERSolf Ctm Oft STS TITIE STATUS u,..a m a EESfglf31BIE M fS) 11 3.3 Fleeding Potentist Cleoed 319566 Protection Requiremente 09/21/97 Crutchfield to WCC 11/09/93 U
cp 11 3.3.1 Capability of Operating Cleoed OS/06/93 to Flent to Cope Utth 910770 O
Design - Beele Flooding Alse 310364 c
Conditiens 310770 A
95/03/83 A. 3. Wong to E. J. Neoczka A07233 II-3.C Safety-Related Water Closed A. 3. % to Supply (tStS)
It. J. Mrocska (FS/12/98 Czwechtteld to WG:
97/79/94 ISER)
II.4.F Settlement of Foundettone II/A and Suried Equipment 111 1 Cleestricetten of "Jpen See Crutchfleid to perf t. J. go en 1.09 Structural C- ; --.nte W. C. Counett tetter.
K. M. Sickles and Systems (Selante 08/12/92. See else and Quality)
FSAR page 3.2.3.
FSAR Change 'sbet tted -
04/20/89. Fellow.wp cent inues en severet open t rees.
otratfl e03
=
Page 2 CUNNECTICUT YANKEE SEP STATUS WFgnTES: 2/1f99 SEP 70ftC ISAP TOrtC DEPARTMENT / PERSON CIASWE OR STS TtT12 STATUS wxa Rr_irvsva lBIE
~ _ -
afS) 111 2 Utad and Tornado imedinge Open Report to 90 percent CCE/U. J. Brtgge E. J. Strocska to Inc 1.06 complete, poed to update 12/28/98 with new switchgear info.
813094 m
Need resolutten of feed-E. J. Streerhe to IRC N
and-bleed tesee.
08/30/39 313346 6*
111-3.A Effects of Illgh Uster Closed W. C. Comnett to Level en Structures W. Feelsen (NRC) 09/26/94 A. 3. Wong to E. J. Wreczke. 03/12/88 111-3.3 Settactural and Other Cleoed Conee pences (e.g.: F1mHR of Safety-Related Equipment in beoemente and reflure of under drain Systems)
Itt-3.C In-Seretco Inspectlen of Cleoed A. B. Wang to 1.29 Water Centret Structures E. J. Itroeska, 95/12/88 SR I
94/97/97 f
111 4.A Tornado liteet tee open See SEP CCE/U. J. Brigge E. J. Stroesha to Imc 1.06 Tepte 111.2 ggfyg/gg st3e94 E. J. Stroetke to Imc 08/30/09 st3346 111-4.5 Turbine Misettes N/A tit-4.C Internally Cenerated Open Pending Completten of CEE/C. R. Ptteen 1.07 Niselles New Switchgear Rece.
1.14 SM.M M
2.
P*S' 3 CourECTICUT YAMEE SEF STAftPS WPBAfts-2/U39 SEF TOPIC ISAF TUFIC DEFARTNENT/ PERSON C1955EE cet STS TIT 12 STATUS (XNSEENTS RESPQtr31312 mar = =rfS1 III-5.A Ptpe Dresks Instdo open open items Answered CFt/D. A. Witchcock 111313 1.3f Centatnsent (sl1313) - AveitIng I2/17/96 NRC Actlen UCC te Zwolinskt
[
111-5.3 Ftpe Sreeks Outside Open Open Items Answered CM/D. A. Ritchcock 312683 o
1.31 Containment 10/23/57 (letter 10/23/87 O
312685)
Questione en states g
Cn of 3 other iteme not addressed in 10/23/97 tetter - Awetting NRC Action 111 6 Selsete Design Open 1.0S ? ;: "..; en Flying Engr./
Spaste provided 06/93/90 1.04 Considerettene Results of 1.04 K. N. Sickles A06968 1.03 Seteetc Evel of AFV CCE/U. J. Stigge 312936 1.03 Fumpheuse (1.04 RMS)
(1.05 WJe)
III-2.9 Design Codes. Design Open Werk (Analysts)
CCE/W. J. Brigge 1.09 Criterte, taed Combine.
Scheduled for tiene, and Reacter Newember 1989 Cavity Design Criterte 111 8.A taese Parte Monitoring Closed Centeldteld to WCC Core Serret vibretten 06/21/82 tit.10 A Thermal Oeerleed open Teregue Switch Settinge DUC OPS /CEE/
S11383 1.10 Fretection for Motore' end t.tett Switch W. N. Seeber JrO to Esslinskt of Mmre Settings 06/2F/93 Freelde final report A06993 to NRC following 1989 settesdnousen to RJN Refweling 10/28/87
..es..mo me.
= >
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Foge A WF987ED: 2/1/99 CDNNECTICI?T TAI 4 TEE SEF STATUS SEP 10FIC DEFAR1NENT/FERSON CIASWER Cet STS TIT 12
$fATUS ColetENTS RESrgPSIRIE
" " ***ffSi ISAF TOPIC 111 10.8 Finer Flywheel Integrity Cleoed Ceeplete if 1905 Serface Rel. Enge./F. M. Austin A02391 OS/2S/92 and Totienetrie Enesina Ammend #SF eten of Flywheele ie 11/12/86 Done Over 10 Teste "U
rp IV-2 Reacttwity Centrol Open Under IL*J Review 1&C/T. J. Norrie F12133 or en C6/30/96 1.54 Systems including A. S. Wang to ERE
[
1.101 Functional Design and 10/18/98 Fretectlen Against (Fine! SEF)
Single Tottu o l
312061 v.S R.C. Fresente soundary Clees 06/26/94 Leekage Detection A. B. Ung to E. J. Wreczka eS/31/e9 Amend $79 v.6 Reacter vessel Integrity Clemed 10/16/93 v.10.A R9E Systes fleet Ex Tube Open Reaguiremente 98eeded for CFI/R. C. Joshi Crutchfleid to WCC et/13/31 Frleary Cootent (STS)
FeIteres (SER)
Cheetstry Limite.
STS Conversten Sheeld Answer Steff*e Concerno.
STS Suh=Itted 06/07/99 0 Fen EECS NCV Freemere CFt/R. C. Josht fMSF. RFf T.10.S R!gR System Reliability 37 08 Intertecho. STS to (STS)
Septre 1.10F In-Service Frier to ate Inteletlen.
STS Sabettted en 06/07/89.
v.11.A Recyriremente for feeletten Open Under rootew in ISAF 1&C/T. J. Norrie 1.02 of NFSI en6 1.FSt
o e
F"G* S CeltetCTICUT YAfEKEE SEP EfAftr5 WF9ATES: I/1/99 SEP TUFlc ISAF TOFIC 98!PastTMUrr/PERSOlt CtbSERg oft STS TITIE STATUS CENWWFT3 RESFOstsISIE 30tM EsttiSi v-11.5 afst System Interlock Cleood Crutchfield to WCC Rep trements 03/03/82 V-12.4 Water Furity of SUR N/A e
Frieery Cootent c
(D VI-1 Orgente Meterfels and Closed SS-11 g
Foetseeidont Cheeietry 3prsry77 CD vt-4 Centateusent toeletten Open Pereenent Exemptlene OtE/C. E. Corneltwo 1.03 System f ree App. J have been CF1/?I. A. Ciccone subeItted on 04/28/89 (813137) and 09/09/89 (813352). IIeed to Sabeit CDC Ceeperison Report.
TI-7.A.3 SCCS Actuetten System N/A TI-7.A.4 Core Spray IIossle N/A Effectinness vt-7.3 ESF Switcheeer free Closed Boolteetti to WDC Injection to Rectreutetten 36/32/9?,
Mode EftSFRFT 84-92 l
19fsrRet 85-32 l
v1 7.C.1 CDC IIe. 17 - Electric Open Pendtag Completten Ctg /W. N. Secher l
1.07 Fever Systees er s ttchgear Roon l
teodificettene i
VI-10.A Teattag of Rosetor Trip Open Inetude adottlenet RFS CFt/R. C. Jeeht CrwtebfleId to WCC l
(sts)
System and Esr Inet dtng sv Teettag and nee,onse 12/e3/06
[
Response Tlee Testing fles Testing In STS.
(SER) l STS Subettted en 06/23/39
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CDInstCTICUT TAIEtEE SEP STATUS WF9ATED: 2/1/99 SEP TOPIC ISAP 10FIC DEPARTMENT / PERSON C128WE em STS TITt2 STAtos ra-efrS at$rgpsIstz mar==rf S1 tit.1.A Isolettee of Reacter open 4 Informel Queettens I6C/v. Norste 12/14/93 1.30 Proteetten Systee free from IIRC Apparently not S19933 Isonsafety Systees.
yet Answered (1984) Info.
313073 provided 01/12/89 (813073) 01/12/99
[
E. J. Nreethe to MC crp VII-3 System Rogetred for Safe closed 95/93/93 Shutdown w
B10779 g
Crutchtfeld to WCC eF/2s/s1 v111 1.A Potential Egetpoent Cleoed Crutchtfeld to Commell rotture Assectated witin 97/22/92 Degraded Crto voltage v1It-2 Oneito Emergency Feuer Cleoed A. B. Wong to System (Diesel Cenerater)
E. 'J. geroeske. 93/31/98 and INSFRFT 97 00 Crutchtfeld to Utc 08/28/81 VItt-3.A Station Settery Capacity open IIe Stetten Bettery Test CFt/R. C. Joshi (STS)
Test Requiremente Requiremente. Ulti be toylemented with STS.
Tech. Spece. Subeltted on 06/10/88. STS to follow.
l 4111-3.3 BC Power System Due vettege Clemed Imey apt SS-91 flonttoring and Annunctatten Crutchfield to IICC 04/26/94 i
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Foge 7 ONWWECTICtif YANKEE SEP STATUS gygnTgy: 2/1/gg SEF 70FIC ISAP TDFIC DEPART,8ENT/ PERSON CtASWE OR STS TIT 12 STATUS u
-u RESP 0gtSIBt2
- - (S) 1X.3 Stetten Servlee end Coeling Cleoed 911192 Unter Systemo 93/30/94 IntC to J. F. Opeke 06/10/9(
T II.S ventitetten Systeme Open Switchgear Rose CEE/C. 7.. Pitman 1.11 ventitetten To se 1.01 Resolved me Part of-N (1.14.2)
ISAP 1.14.2 (New O
Switchgear Room) 1999 IV-1 Decrease in Feedester Cleoed SEP Evelmetten of the I&C/v. J. Blezzle 312133 1.101 Temp. Increase in incrosse in Feed Flow 06/30/96 Feedwater Flow snereese Event Isew Cleoed 17nder A. S. Wang to EJet in Steam Flow and inadvertent ISAP Review.
19/13/g3 Opening of a S/C Reg. Velve IV.2 Spectrum of Steese Systee Open STS Liette on ledine CFI/R. C. Jeeht A6M49 (STS)
Piping Fellereo Inside Activity. STS Subettted 09/08/92 and Outeide Centatraent On 06/02/89 UCC to Crutchfield IV.3 1mee of Estornet taed, N/A Tterbine Trty, taso of Condenser vaco m. Cleeure of stSIV and Steen Pressure Reguteter Fallere IV 7 Rx Coelant Puey Roter Cleoed STS Liette en ledine CFt/R. C. Josht A92179 Seteele end Reactor Activity. STS Subeltted 03/01/32 Coolant Pump Shaft treek en 06/07/89 uCC to Ceutchfield 312133
(
e6/30/96 A. B. Weeg to EMI 10/10/98 enests.oes l
l
Fees a COIgetCTICEFT TAMEEE SEP STATUS WF94TW: 2/1/99 StF TOPIC 1SAF TOPIC DEFAR1NEPf/FWLW ftM OR STS TfTL' STAftlS ia RESFORSiBIE
.IS1 S eetrue of Red tjoction Cleeed STS t.tette en tedine Crt/It. c. Joshi A42613 XV-12 F
Aceidonte Actieity. STS Subeitted 99/16/92 en 06/02/89.
A. 3. Ifeng to RJII 10/19/88 m
cu IV.16 Radielsgfeel Consequences Open STS 1.tette en ledine CF1/R. C. Jeohi NEIR9C Sf6
(??S) of reilure of Small E.iner Acetwity. STS Subettted Sec. 4.35 fV Cerrying Frie. t.eet, en 06/07/99.
Cateide Centeineent.
27 17 Red C-z.. n:ee of S/C Closed STS Liette en Iodine CFI/R. C. Joshi 312133 Tube Fellare.
Activity. STS Submitted 06/30/96 en 06/07/89.
A. 3 weng to E.Mt 10/1s/e8 29 10 sted. Consequences of Main N/A Steam t.1no Failore Oute1de Centeinonett 27 19 IDCAs mesultf ag from Clee*d Crutetsfteld to IIOC Spectrue of Poetulated 90/27/92 Ftpo Brooke Utthin RCFS IIRetEY Total open Str TOPICS 21 Open topico in ISAF 12 Awetting NRC cloeure J
Open topico eevered by STS conversten
.3
..ee.se aos l
IIevenber 7 1990 0
~Page I of 7 Millstone thtt No.1 SEP STATUS.
SEP Topic 100.
Department \\ Person (ISAP100.)
Title Status Cossents Responsible Closure Document 11-3.8 Flooding Elevation; Open Proposed clesfrg in September 29. 1989 SER freer allt October 7.1995 11-3.B.1 Intake Structure; ISAP Report, pending Staff review cf coverlag all ef these toples 11-3.0 Local Flooding; submitted information (TAC f49780).
except scuppers and fire peep (1.19)
Gas Turbine Butiding; house blockwalls.
Diesel Fuel Cil, Emergency Procedures II-4.F Turbine Building; Closed M. L. Boyle letter te (1.19)
Gas Turbine Generator E. J. Mroczka. Jaesary 4.1996.
Building; Buried Pipelines m
oc' III-I Radiography Require-Closed Submittal of tlFSAR on m
(1.15) ments Fracture Toughness; Marth 27. 1987 Draft Valves; NUREG-1184, dated April 2 N
Pumps; 1987.
N Storage Tanks III-2 Wind and Tornado Open Proposed closing in Septeu6er 29, 1989 5tR from NRC dated (1.19) toadings ISAP Report, pending Staff review of flo d r 25. 1985.
subeltted informatIon.
III-3.A Flood Elevation; Open Proposed closing In September 29. 1989 SER October 7. 1985.
(1.19)
Groundwater ISAP Report, pending Staff review of subeltted infornatfon.
l t
L. L. 7. 1990 Page 2 of 7 Millstone Unit No. I StP STATUS SEP Topic No.
Department \\ Person (ISAP No.)
Title Status Ceaments Responsible Closure Document-III-3.C Structures and Coupownts Closed Subetttal of UFSAR in March of (1.15)
Requiring Inspection and 1987. ISAP submittal dated Inspection Progran Nevea6er 9,1968. Draft-NUREG-II84, dated April 2.
1987.
III-4.A Tornado Missiles Open Being tracked as part of ISAP.
GME/C. D. Marson J. J. Shea letter to (1.02)
IIS plans completten in late W. G. CounsII, dated May 25 1990.
1982.
III-4.8 Turbine Missiles Open Awaiting closefre by NRC.
W. G. Counsti letter to a',
J. A. Zwolinskt, dated December 5, 1984.
c (D III-4.C Internally Generated Closed IPSAR, Section 3.1.
m Missiles w
III-5.A Cascading Pipe Breaks; Closed Jet Ispingement, and Pipe IPSAR 5epplement Section 2.7.
Whip III-5.B Moderate-Energy Piping, Closed SER from NRC on June 29 Jet taptagement, and Unfsolable Breaks 1983 and IPSAR Section 2.8.
III-6 Seismic Design Consi-Open Proposed closing in September 29, (1.19 and derations 1989 ISAP Report, pending Staff I.%)
review of submitted review of setzeitted infonmation.
Information.
R Ilovember 7. 1990-Page 3 sf 7 a
Millstone Unit feo. I SEP STATM SEP Topic les.
Department \\ Person (ISAPflo.)
Title Status Comments Responsible Closure Document III-7.B Design Codes.' Design Closed M. L. Boyle letter to (I.19)
Criteria. Load Combina-E. J. Mroczka. dated January 4..
tions and Reactor Cavity 1990.
Design Criteria III-8.A Loose-Parts Monitoring Closed Issue deleted March 3, 1982.
and Core Barrel Vibration Monitoring III-10.A Thermel-Overload Protec-Closed SER from IIllC tion for Motors of Motor- -
September 16. 1985. IPSAR Operated Valves Supplement Section 2.11.
IV-2 Reactivity Control Closed Amendment #97 to License.
m Systems-(
cv I
C Y-5 Reactor Coolant l'ressure Closed Amendment #97 to License.
Boundary Leakaga Detection i
'j N
A V-6 Reactor Vesse'l Integrity Closed D. M. Crutchfleid letter to l
W. G. Counsil. August 28. 1987.
Y-IO.A Residual Heat Removal Closed IPSAR. Sectlen 3.I.
l System Heat Exchanger Tebe Failure I
V-IO.B Residual Heat Removal Closed IPSAR Sopplement Section 4 System Reliability I
4 I
l
^ ^' '
ho d e 7. 1990 Page 4 ef 7 Millstone Unit No. I SEP STATUS SEP Topic No.
Department \\ Person (ISAP No.)
Title Status Ceaunents Responsible Closure Docsuent Y-II.A Requirements for Closed Draft MUREG-Il84, dated April 2.
(I.04)
Isolatten of High-and 1987.
Low. Pressure systems V-II.8 RHR System Interlock Closed IPSAR. Section 3.1 Requirements V-12.A Water Cheef stry Limits Closed Amendment #99 to License.
VI-I Organic Naterials and Closed J. Shee to V. G. Counsil Post Accident Chemistry February 25, 1962.
VI-4 Containment Isolation Closed g
(1.03)
SER from the staff en July 7 1983.
e
<D VI-7.A.3 ECCS Actuation System Closed SER from the staff dated y
July 5, 1983.
VI-7.A.4 Core Spray Nozzle Closed IPSAR Section 4.22.
Effectiveness VI-7.C.]
Redundant Onsite Power Open Awalting NRC closure. (TAC #49384)
ISAP submittal dated November 9, (1.21)
Systems 1988.
Noveder 7.1990 Page 5 ef 7 Millstone Unit No. I StP STATUS SEP Topic No.
Department \\ Person (ISAP No.)
Title Status Cournents Responsible Ciestre Decament VI-IO.A Testing of RTS and ESF Closed IPSAR Supplement, Section 4.
(1.22)
VII-1.A Isolation Devices Open Awalting SER from the Staff.
Between Reactor Protection System (RPS) and Monitoring Systems VII-3 Systees pequired for Closed Safe Shutdown IPSAR Section 4.2.6.
VIII.I.A Potential Equipment Open Work was completed during 1989 (1.25)
Failures Associated Refueling Outage (TAC F60207). By with Degraded Grid letter dated 1/20/90, NNECO responded u
Voltage to Staff's 5/31/89 letter which m
identified new concerns with the y
toss of Normal Power (LNP) logic.
Independent of Staff's new concern, r0 O
NNECO considers this specific issue resolved. NRC closecut required.
NNECO provided ulditional Information relating to the Ml11 stone Unit No. I LMP logic in a letter dated 10/30/90.
VIII.2 Onsite Emergency Power Open Avalting closure by NRC (TAC #49387).
SER from NRC, dated August I6, (1.22)
Systems 1984 ISAP submittal dated Setember 29, 1989.
VIII-3.A Station Battery Test Closed Requirements Amendment F99 to License.
4
/
5
q Nevenber 7,1990 '
Page 6 sf 7 Millstone Unit No. I SEP STATUS SEP Topic No.
Department \\ Person (ISAP No.)
Title States-Comuments Responsible Closure Document VIII-3.8
' D.C. Power System Bus Open Work was completed during 1989 SER free NRC January 7 s-(1.25)
Voltage Monitoring eM Refueling Outage (TAC #60207).
1986 closed part of this Annunciation; By letter dated 7/20/90 NMECO topic.
Battery Status Alarms and responded to Staff's 5/31/89 letter Indications which fdentified new concerns with the Loss of Normal Power (LMP) logic.
Indeps.or.t of Staff's new concern, MNEE0 considers this specification issue resolved. NRC closecut required.
NNE00 provided additional information relating to the Millstone Unit No. I LMP logic in a letter dated 10/30/90.
IX-3 Station Service and Closed y
Cooling Water Systems IPSAR Section 4.31.
os C
IX-5
' Ventilation Systems Closed (1.05)
SER frem the Staff on September 14, 1932.
ru N
IV-1 Decrease in Feedwater Closed SER from NRC Temperattere. Increase in December 31, 1981.
flow, Increase in Steam flow, and Inadvertent Opening of a steam Generator Relief or Safety Valve.
L. 4., 7. 1990 Pay T of 7 Millstone thalt No. I SEP STATUS SEP Topic 100.
Department \\ Person (ISAP100.)
Title Status Comments Responsible Ctesore Document IV-3 Loss of External Load Closed IPSAR Section 4.34.
Turbine Trip Loss of Condenser Vacuum.
Closure of Main Steam Isolation Valve (BWR),
and Steam Pressere Regulator Failures (Closed)
IV-7 Reactor Coolant Pump Closed D. M. Crutchfield to Rotor Seizure and Shaft W. G. Counsif. December 4, i
Break 1981. IPSAR. Section 3.1
[ IV-16 Radiological Consequen-Closed Amew hent #99 to license to ces of Failure of Small and IIRC SER June 21. IW.
rD Lines Carrying Primary Coolant Outside Containment.
g Co IV-18 Radiological Consequen-- Closed Amendsee.t #99 to license and ces of a Main Steam Line 18EC SER Jent-71. 1984 Failure Outside Containment.
IV-19 LOCAs Resulting From Closed IPSAR. Section 3.i.
Spectrum of Postulated Pfpe Breaks Within RCPB Suumery:
Total Open SEP Tepics 11 Awaiting NRC closure 10 Open Topics Scheduled in ISAP/IIS I
v,
.g FACILITY NAME: Haddam Neck Plant DOCKET NO.:
50-213 LICENSEE:
' Connecticut Yankee Atomic Power Company STATUS OF LICENSEE IMPLEMENTATION OF GENERIC SAFETY ISSUES RESOLVED WITH IMPOSITION OF REQUIREMENTS OR CORRECTIVE ACTIONS GSI/(MPA No.)
Title Applicability.
Status
- Comments 40 (8065)'
Safety Concerns Associated'With All BWRs N/A Pipe Breaks in the BWR Scram System 41 (8058)
BWR Scram Discharge Volume Systems All BWRs N/A 43 (B107)
Reliability of Air Systems
- ?
.All Plants C
Closed by CYAPC0 sub-mittal dated 10/12/90.
e
- 51 (L913)
Improving the Reliability of Open-All Plants I
ISAP Topic 1.120, sub-
[j Cycle Service Water Systems mittal dated 4/30/90.
67.3.3 (A017)
Improved Accident Monitoring All Plants I
ISAP Topic 1.21, sub-mittal dated 4/30/90.
75 (8076)
Item 1.1--Post-Trip Review (Program
' All Plants C
Lioseo oy NRC SER Description and "rocedure)'
dated 3/20/85.
75 (8085)
Item 1.2--Post-Trip Review--Data All Plants C
Closed by NRC SER and Information Capability dated 7/3/85.
75 (B077)
Item 2.1--Equipment Classification All Plants C
Closed by NRC SERs and Vendor Interface (Reactor Trip dated 8/15/86 and System Components) 4/22/87.
t Haddam Neck Plant f
GSI/(MPA No.)
Title Applicability Status
- Comments 75 (8086)
Item 2.2.1--Equipment Classification All Plants C
Closed by ISAP Topic for Safety-Related Components 1.36, submittal dated 4/30/90.
75 (LOO 3)
Items 2.2.2--Vendor Interface.for All Plants C
ISAP Topic 1.36 and NRC SER dated 5/27/87.
Safety-Related Components NNECO addressed open issues in response to GL 90-03, dated 9/24/90.
]
75 (8078)
{tems 3.1.1 & 3.1.2 -Post-All Plants C
Closed by NRC SER Maintenance Testing (Reactor Trip dated 2/21/86.
System Components)
.g 75 (B079)
Item 3.1.3--Post-Maintenance Test-All Plants C
Closed by NRC SER o
ing--Changes to Test Requirements dated 10/16/85.
o (Reactor Trip System Components) too 75 (8087)
Items 3.2.1 & 3.2.2--Post-All Plants C
Closed by NRC SER Maintenance Testing (All Other dated 2/21/86.
Safety-Related Components) 75 (8088)
Item 3.2.3--Post-Maintenanec fest-All Plants C
Closed by NRC SER ing--Changes to Test Requirements dated 10/16/85.
(All Other Safety-Related Compo-nents) 75 (8080)
Item 4.1--Reactor Trip System All P? ante C
Closed by NRC SER Reliability (Vendor-Related Modi-dated 2/21/86.
fications) l Haddam Neck Plant _ _ - _ -
.s i
GSI/(MPA No.)
Title
' Applicibility
. Status
- Comments' l'
75.(8081)
Items 4.2.1 & 4.2.2--Reactor Trip All PWRs C-Closed by NRC'SER' l
- System Reliability--Maintenance and dated 7/1/85.
1
'TestingL(Preventative Maintenance i
and' Surveillance Program for Reactor Trip Breakers) 75 (8082)
' Item 4.3--Reactor Trip System All;W and C
Closed by NRC SER
- Reliability--Design Modifications' B&W Plants dated 4/26/90.
i-(Automatic Actuation-of Shunt Trip Attachment'for Westinghouse and
~
B&W Plants) t 75 (B090)
Item 4.3--Reactor Trip System All W and C
Closed by NRC SER l
Reliability--Tech Spec Changes-B&W' Plants' dated 4/26/90.
l (Automatic Actuation of Shunt Trip 1
y Attachment for Westinghouse and B&W Plants) o
$ 75 (8091)
Item 4.4--Reactor Trip System All B&W N/A l
Reliability (Improvements in Plants
- Maintenance and Test' Procedures for B&W Plants) i 75 (8092)
Item 4.5.1--Reactor Trip System All Plants C
Closed by NRC SER Reliability--Diverse. Trip Features dated 2/21/86.
(System Functional Testing)
(
75-(8093)
Items 4.5.2 & 4.5.3--Reactor Trip All Plants C
Closed by NRC. letter System Reliability--Test Alterna-dated 6/20/89.
tives and Intervals (System Func-
[
tional' Testing) 86 (B084) long Range Plan for Dealing With All BWRs N/A i
Stress Corrosion Cracking-in'BWR Piping Haddam Neck Plant '
1 w
~
e
+..-e..
GSI/(MPA No.1-Title
-Applicability Status *'
Comments 93 (8098)
Steam Binding of Auxiliary. Feed-.
All PWEs C.
Closed by ISAP Topic 1.58 submittal dated water Pumps 3/2/89.
99 (L817)
RCS/RHR Suction Line Valve Inter-All PWRs I
ISAP Topic 1.115 sub-.
lock on PWRs (11/91) mittal dated 4/30/90.-
t 124 Auxiliary Feedwater System Relia-ANO-l&2, N/A bility Rancho Seco, Prairie Island I&2,.
Crystal River-3 Ft.'Calhoun
'o A-13-(8017)
Snubber Operability Assurance--
All Plants C
. Closed by ISAP Topic j$
Hydraulic Snubbers 1.24, NRC. letter dated l
8/18/87.
A-13 (8022)
Snubber Operability Assurance--
All Plants C
Closed by ISAP Topic Mechanical Snubbers 1.25, NRC letter dated 8/18/87.
]
A-16 (0012)
Steam Effects on BWR Core Spray Oyster Creek N/A l'
Distribution
& NMP-1 A-3S (8023)
Adequacy of Offsite Power Systems All Plants C
Closed by NRC SER dated 4/26/90.
B-10 Behavior of BWR Mark III Contain-All BWR N/A ments Mark III Plants Haddam Neck Plant __
~
GSI/(MPA i _.
Title ADDlicability
. Status
- Comments t
B-36 Davelop Design,: Testing and Main -
All' Plants.
N/A t-iance Criteria for Atmosphere With OL' r
C'eeanup' System Air Filtration and
' Applications Adsorption Units for_ Engineered After 04/01/80 Safety. Features-Systems and for Norwal' Ventilation Systems B-63 (8045)
Isolation of Low Pressure Systems All Plants I
ISAP Topic 1.02 sub-Connected.to the Reactor toolant' mittal dated 4/30/90.
4 System Pressure Boundary 27
'8 f
Haddam Neck' Plan't,
~:.
FACILITY NAME: Millstone Nuclear Power Station, Unit No. 1 DOCKET NO.:
50-245 LICENSEE:
Northeast Nuclear Energy Cocpany.
STATUS OF' LICENSEE IMPLEMENTATION OF GENERIC $AFETY ISSUES RESOLVED WITH IMPOSITION OF REOUIREMENTS OR CORRECTIVE' ACTIONS GSI/(MPA No.)
Title Applicability Status
- Comments 40 (B065)
Safety Cencerns Associated liith.
All BWRs C'
' Addressed under ISAP.
Pipe Breaks in the BWR Scram' System Topic 1.29.
Closed by NRC in NUREG-ll84.
41 (5058)
BWR Scram Discharge. Volume Systems All BWRs
'C License Amendment #86, dated 11/12/82.
43 (B107)
Reliability of ' Air Systems All Plants I
NNECO submittals dated (6/91) 5/4/90,6/11/90,and y
7/11/90.
51 (L913)
Improving the Reliability of Open-All Plants I
' Addressed Under ISAP l
Cycle Serv 8ce Water Systems (5/93)
Topic 1.112. NNECO submittals dated 1/25/90 and 6/1/90.
'III 67.3.3 (A017)
Improved Accident Monitoring All Plants I
75 (8076)
Item 1.1--Post-Trip Review (Program All Plants C
Closed by NRC SER Description and Procedure) dai.sd 4/5/85.
(1) NNECO submittal dated 5/31/84 addressed compliance with R.G. 1.97'for Millstone Unit No. I.
Open items addressed under ISAP Topic 1.09.
NNECO will provide results of review of main feedwater flow and l
cooling water flow to ESF system components in future ISAP/IIS update report. NRC closeout of other open items required.
Millstone' Unit No. 1.
~
GSI/(MPA No.1 Title' Applicability Status
- Comments 75 (8085)
Item 1.2--Post-Trip Review--Data All Plants C
Addressed under ISAP and Information Capability.
Topic 1.30.
Closed by NRC SER dated 6/24/86.
75 (8077)
Item 2.1--Equipment Classification All Plants C
Addressed Under ISAP and Vendor Interface (Reactor Trip Topic 1.26.
Closed by j
t NRC SERs dated System Components) 11/24/86 and 8/4/87.
75 (8086)
Item 2.2.1--Equipment Classification All Plants C
Addressed Under ISAP for Safety-Related Components Topic 1.31.
Closed by NRC SER dated 10/31/d8.
75 (LOO 3)
Items 2.2.2--Vendor Interface for All Plants C
Addressed under ISAP Safety-Related Components Topic I.31.
'a j$
addressed open issues in response to GL 90-03, dated co 9/24/90.
75 (8078)
Items 3.1.' & 3.1.2--Post-All Plants C
Addressed under ISAP Maintenanca Testing (Reactor Trip Topic I.27.
Closed by System Corponents)
NRC SER dated 2/21/86.
75 (8079)
Item 3.1.3--Post-Maintenance Test-All Plants C
Addressed un(2r ISAP ing--Changes to Test Requirements Topic 1.28.
Closed by (Reactor Trip System Components)
NRC SER dated 9/3/85.
75 (8087)
Items 3.2.1 & 3.2.2--Post-All Plants C
Addressed Under ISAP Maintenance Testing (All Other Topic 1.32.
Closed by Safety-Related Components)
NRC SER dated 2/21/86.
75 (8088)
Item 3.2.3--Post-Maintenance Test-All Plants C
Addressed Under ISAP ing--Changes to Test Requirements Topic I.33.
Closed by (All Other Safety-Related Compo-NRC SER dated 9/3/85.
nents)
Millstone Unit No. 1 ^
~
GSI/(MPA No.)
Title Applicability Status
- Comments 75 (8080)
Item 4.I--Reactor Trip System All Plants C
Closed by NRC SER Reliability (Vendor-Related Modi-dated 2/21/86.
fications) 75 (8081)
Items 4.2.I & 4.2.2--Reactor Trip All PWRs N/A System Reliability--Maintenance and Testing (Preventative Maintenance and Surveillance Program for Reactor Trip Breakers) 75 (8082)
Item 4.3--Reactor Trip System All W and N/A Reliability--Design Modifications B&W Plants (Automatic Actuation of Shunt Trip Attachment fer Westinghouse aad B&W Plants)
-o 55 75 (8090)
Item 8.3--Reactor Trip System All W and N/A Reliability -Tech Spec Changes B&W Plants g(
(Automatic Actuation of Shunt Trip Attachment for Westinghouse and B&W Plants) 75 (8091)
Item 4.4--Reactor Trip System All B&W N/A i
Reliability (Improvements in Plants Maintenance and Test Procedures for B&W Plants) l
(
75 (8092)
Item 4.5.I--Reactor Trip System All Plants C
Addressed under ISAP Reliability--Diverse Trip Features Topic I.35.
Closed by (System Functional Testing)
NRC SER dated 2/21/86.
75(8093)
Items 4.5.2 & 4.5.3--Reactor Trip All Plants C
Addressed Under ISAP System Reliability--Test Alterna-Topic 1.34 Closed by tives and Intervals (System Func-NRC SER dated 5/31/89.
tional Testing)
Millstone Unit No. I
'.31/(MPA No.)
Title Acolicability Status
- Co w nts 86 (8084) long Range Plan for Dealing With All BWRs I
Partially closed by Stress Corrosion Cracking in BWR (12/90)
NRC SER dated 12/1/89.
Piping NNECO evaluating Tech.
Spec. requirements.
93 (8098)
Steam Binding of 8.sxiliary Feed-All PWRs N/A water Pumps 99 (L817)
RCS/RHR Suction Line Valve Inter-All PWRs N/A lock on PWRs 124 Auxiliary Feedwater System Relia-ANO-l&2, N/A bility Rancho Seco, Prairie Island 1&2, Crystal u
River-3 g
Ft. Calhoun n>
A-13 (8017)
Snubber Operability Assurance--
All Plants C
License Amendment #15, Hydraulic Snubbers dated 3/17/88.
1 A-13 (8022)
Snubber Operability Assurance--
All Plants C
License Amendment #15, Mechanical Snubbers 3/I7/88.
A-16 (D012)
Steam Effects on BWR Core Spray Oyster Creek N/A Distribution
& NMP-I Millstone Unit Mu. 1 l
?
GSI/(MPA No.1 Title Aeolicabili_t1 Status
- Comments (2)
(
A-35 (B023)'
Adequacy of Offsite Power Systems All' Plants C
B-10 Behavior of BWR Mark III Contain-All BWR N/A ments Mark III j
Plants B-36 Develop Design, Testing and Main-All Plants N/A 1.
tenance Criteria for Atmosphere-With OL Cleanup System Air filtration and Applications Adsorptica Units for Engineered After 04/01/80 i
Safety Features Systems and for i
Normal Ventilation Systems B-63 (8045)
Isolation of Low Pressure Systems All Plants C
NNECO submittal dated Connected to the Reactor Coolant 3/18/80. Addressed i
y System Pressure Boundary under SEP Topic V-II.A e
ISAP Topic 1.04.
Closed by NRC in g
NUREG-II84.
1 l
i l
t r
1 l
(2) Addressed Under ISAP Topics 1.23 and 1.25. By letter dated 7/20/90, NNECO responded to Staff's 5/31/89 letter which identified new concerns with the loss of normal power (thP) logic.
I-4;rc.-Jer,t of the I
Staff's new concern, NNECO considers this specific issue resolved. NRC closecut required. NNECO l
provided additional information relating to the Millstone Unit No. I LMP logic in a letter dated j'
10/30/90.
i l
Millstone Unit No. 1 l
i-j-
FACILITY NAME: Millstone Nuclear Power Station, Unit No. 2 DOCKET NO.:'
50-336 LICENSEE:
Northeast Nuclear Energy Company l
l STATUS OF LICENSEE IMPLEMENTATION OF GENERIC SAFETY ISSUES RESOLVED WITH IMPOSITION OF REQUIREMENTS OR CORRECTIVE ACTIONS' GSI/(MPA No.)
Title Applicability Status
- Comments 40 ' L S)
Safety Concerns Associated With All BWRs N/A Pipe Breaks in the CWR Scram System 41 (8058)
BWR Scram Discharge Volume Systems All BWRs N/A 43 (BIO 7)
Reliability of Air Systems All Plants C
Closed by NNECO sub-y mittal dated 5/4/90.
Closed by MRC letter e*
dated 6/28/90.
51 (L913)
Improving the Reliability of Open-All Plants I
NNECO submittal dated Cycle Service Water Systems (1/91) 1/25/90.
67.3.3 (A017)
Improved Accident Monitoring All Plants C
Closed by NNECO sub-mittal dated 6/20/88.
75 (B076)
Item 1.1--Post-Trip Review (Program All Plants C
Closed by NRC SER Lescription and Procedure) dated 7/10/85.
75 (B085)
Item 1.2--Post-Trip Review--Data All Plants C
Closed by MRC SER and Information Capability dated 6/12/86.
75 (8077)
Item 2.1--Equipment Classification All Plants C
Closed by NRC SER and Vendor Ir.terface (Reactor Trip dated 7/27/87.
System Components) 75 (B086)
Item 2.2.1--Equipment Classification All Plants C
Closed by NRC SER for Safety-Related Components dated 10/31/88.
f Millstone Unit No. 2 a
GSI/(MPA No.)
' Title
. Applicability Status
- Comments 75 (LOO 3)
Items 2.2.2--Vendor Interface for All Plants C
NNECO addressed open Safety-Related Components issues in response to GL 90-03, dated 9/24/90.
75 (8078)
Items 3.1.1 & 3.1.2--Post-All Plants C
Closed by NRC SER Maintenance Testing (Reactor Trip dated 3/18/86.
System Components) 75 (8079)
Item 3.1.3--Post-Maintenance Test-All Plants C
Closed by NRC SER ing--Changes to Test Requirements dated 10/24/85.
l (Reactor Trip System Components) 75 (8087)
Items 3.2.1 & 3.2.2--Post-All Plants C
Closed by NRC SER Maintenance Testing (All Other dated 3/18/86.
- 7 Safety-Related Components) e*
75 (8088)
Item 3.2.3--Post-Maintenance Test-All' Plants C
Closed by NRC SER ing--Changes to Test Requirements dated 10/24/85.
A<"
(All Other Safety-Related Compo-nents) 75 (8080)
Item 4.1--Reactor Trip System All Plants C
Closed by NRC SCR Reliability (Vendor-Related Modi-dated 3/18/86.
fications) 75 (8081)
Items 4.2.1 & 4.2.2--Reactor Trip All PWRs C
Closed by NRC SER System Reliability--Maintenance and dated 4/10/86.
4 Testing (Preventative Maintenance and Surveillance Program for Reactor l
Trip Breakers) 75 (8082)
Item 4.3--Reactor Trip System All W and N/A Reliability--Design Modifications B&W Plants (Automatic Actuation of Shunt Trip Attachment for Westinghouse and B&W Plants)
Millstone Unit No. 2 -
k GSI/(MPA No.)
Title ADDliCabilitY' Status
- CoEgents 75'(8090)
Item 4.3--Reactor Trip System All W and" N/A Reliability--Tech Spec Changes _
B&W Plants (Automatic Actuation of Shunt Trip Attachment for Westinghouse and i
B&W Plants)
L 75 (8091);
Item 4.4--Reactor Trip System All B&W N/A Reliability (Improvements in Plants Maintenance and Test Procedures for_B&W Plants) 75 (B092)
Item 4.5.1--Reactor Trip System All Plants C
Closed by NRC SER Reliability--Diverse Trip Features dated 3/18/86.
(System Functional Testing) i-y 75 (B093)
' Items 4.5.2 & 4.5.3--Reactor Trip All Plants C
Closed by NRC SERs System Reliability--Test Alterna-dated 4/26/89 and e*
tives and Intervals (System Func-6/21/89.
3 tional Testing) 86 (8084) long Range Plan for Dealing With All BWRs N/A Stress Corrosion Cracking in BWR l
Piping 93 (B098)
Steam Binding of Auxiliary Feed-All PWRs C
Closed by NNECO response water Pumps to IEB 85-01, dated 2/28/86.
99 (L817)
RCS/RHR Suction Line Valve Inter-All PWRs I
Work to be completed
]
lock on PWRs (6/92) during Cycle 11 refueling outage.
i I
i l'
l Millstone Unit No. 2 1
l l :-
GSI/(MPA No.'l-Title ADDlicability Status
- Comments 124 Auxiliary Feedwater System Relia-ANO-1&2, M/A bility Rancho Seco, Prairie Island 1&2, Crysta1 River-3 l
Ft. Calhoun A-13 (B017)
Snubber Operability Assurance--
All Plants C
License Amendment #118, Hydraulic Snubbers dated 9/1/87.
A-13 (B022)
Snubber Operability Assurance--
All Plants C
License Amendment #118, Mechanical Snubbers dated 9/1/87.
A-16 (D012)
Steam Effects on BWR Core Spray Oyster Creek N/A 4
y Distribution
& NMP-1 e
- A-35 (B023)
Adequacy of Offsite Power Systems All Plants C
License Amendment #16, g
dated 7/30/76.
B-10 Behavior of BWR Mark III Contain-All BWR N/A ments Mark III Plants t
B-36 Develop Design, Testing and Main-All Plants N/A tenance Criteria for Atmosphere With OL l
Cleanup System Air Filtration and Applications Adsorption Units for Engineered After 04/01/80 Safety Features Systems and for Normal Ventilation Systems i
B-63 (8045)
Isolation of low Pressure Systems All Plants C
Closed by NNECO response i
Connected to the Reactor Coolant (dated 3/18/80) to NRC System Pressure Boundary request for information (dated 2/23/80).
i Millstone Unit No. 2 :
FACILITY NAME: Millstone Nuclear Power Station, Unit No. 3 DOCKET NO.:
50-423 LICENSEE:
Northeast Nuclear Energy Company STATUS OF LICENSEE IMPLEMENTATION OF GENERIC SAFETY ISSUES RESOLVED WITH IMPOSITION OF REQUIREMENTS OR CORRECTIVE ACTIONS GSI/(MPA No.)
Title Acolicability Status
- Comments 4
40 (B065)
Safety Concerns Associated With All BWRs N/A 1
Pipe Breaks in the BWR Scram System 41 (8058)
BWR Scram Discharge Volume Systems All BWRs N/A i
43 (8107)
Reliability of Air Systems All Plants C
Closed by NRC letter
'y dated 5/5/89.
o*
51 (L913)
Improving the Reliability of Open-All Plants I
NNECO letter of
[3 Cycle Service Water Systems (3/91) 1/25/90.
67.3.3 (A017)
Improved Accident Monitoring All Plants C
Closed by NUREG 1031, Supplement #4 and NRC letter dated 10/21/87.
75 (8076)
Item 1.1--Post-Trip Review (Program All Plants C
Closed by NUREG 1031, i
Description and Procedure)
Supplement #4.
75 (8085)
Item 1.2--Post-Trip Review--Data All Plants C
Closed by NRC letter and Information Capability dated 11/24/86.
75 (B077)
Item 2.1--Equipment Classification All Plants C
Closed by NRC letters and Vendor Interface (Reactor Trip dated 11/24/86 and System Components) 8/4/87.
75 (8086)
Item 2.2.1--Equipment Classification
'All Plants C
Closed by NRC letter for Safety-Related Components dated 10/31/88.
Millstone Unit No. 3
-I-i 6
o GSI/(MPA No.)
Title Applicability Status
- Comments 75 (LOO 3)
Items 2.2.2--Vendor Interface for All Plants C
NNECO addressed open Safety-Related Components issues in response to GL 90-03, dated 9/24/90.
75 (8078)
Items 3.1.1 & 3.1.2--Post-All Plants C
Closed by NRC letter Maintenance. Testing (Reactor Trip dated 6/26/87.
System Components) 75 (B079)
Item 3.1.3--Post-Maintenance Test-All Plants C
Closed by NRC letter ing--Changes to Test Requirements dated 11/24/86.
(Reactor Trip System Components) 75 (8087)
Items 3.2.1 &i3.2.2--Post-All Plants C
Closed by NRC letter Maintenance Testing (All Other dated 6/26/87.
y Safety-Related Components)
N 75 (8088)
Item 3.2.3--Post-Maintenance Test-All Plants C
Closed by NRC letter ing--Changes to Test Requirements dated 11/24/86.
a (All Other Safety-Related Compo-nents) 75 (8080)
Item 4.1--Reactor Trip System All Plants C
Closed by NRC letter Reliability (Vendor-Related Modi-dated 11/24/86.
fications) 75 (8081)
Items 4.2.1 & 4.2.2--Reactor Trip All PWRs C
Closed by NRC letter System Reliability--Maintenance and dated 11/24/96.
Testing-(Preventative Maintenance and Surveillance Program for Reactor Trip Breakers).
75 (8082)
Item 4.3--Reactor Trip System All W and C
Closed by NUREG 1031.
Reliability--Design Modifications B&W Plants I
i (Automatic Actuation of Shunt Trip Attachment for Westinghouse and B&W Plants)
Millstone Unit No. 3 l l
1,..3 4
'E-"-"--Y
,.,i-
....s._sur y:r.
1-y-e-
t GSIM MPA No.)
Title Apolicability Status
- Comments i.
l 75 (8090)
Item 4.3--Reactor Trip System All W and C
Closed by LRC letter Reliability--Tech Spec Changes B&W Plants dated 8/7/87.
(Automatic Actuation of Shunt Trip 2
Attachment for Westinghouse and j
B&W Plants) i 75 (8091)
Item 4.4--Reactor Trip System All B&W N/A i
Reliability (Improvements in Plants Maintenance and Test Procedures for B&W Plants) 75 (8092)
Item 4.5.1--Reactor Trip System All Plants C
Closed by NRL letter Reliability--Diverse Trip Features dated 6/26/87.
4 j
(System Functional Testing)
}
75 (B093)
Items 4.5.2 & 4.5.3--Reactor Trip All Plants C
Closed by NRC letters o
E System Reliability--Test Alterna-dated 2/24/87 and
}.
tives and Intervals (System Func-6/19/89.
g tional Testing) 86 (8084) long Range Plan for Dealing With All BWRs N/A
}
Stress Corrosion Cracking in BWR l
Piping 93 (8098)
Steam Binding of Auxiliary Feed-All PWRs C
Closed by MRC letter water Pumps dated 6/29/88.
i i
99 (t817)
RCS/RHR Suction Line Valve Inter-All PWRs I
. Work to be completed lock on PWRs (2/91) during third refueling j
outage.
I 124 Auxiliary Feedwater System Relia-ANO-182.
NC NUREG 1031.
bility Rancho Seco, i
Prairie l
Island-1&2, Crystal River-3 Millstone. Unit No. 3 l l
i ~.
i GSI/(NPA No.1 Title Acclicability Status
- Comments i
Ft. Calhoun f
i A-13 (8017)
Snubber Operability Assurance--
All Plants NC NUREG 1031.
Hydraulic Snubbers A-13 (8022)
Snubber Operability Assurance--
All Plants NC NUREG 1031.
l 3
t Mechanical Snubbers-A-16 (D012)
Steam Effects on BWR Core Spray Oyster Creek
'N/A Distribution
& NNP-I j
A-35 (8023)
Adequacy of Offsite Power Systems All Plants NC NUREG 1031.
l B-10 Behavior of BWR Nark III Contain-
.All BWR N/A
[
ments Mark III r
l y
Plants
[
e
- B-36 Develop Design, Testing and Main-All Plants NC NUREG 1031.
a tenance Criteria for Atmosphere With OL j
Cleanup System Air Filtration and Applications l
Adsorption Units for Engineered After 04/01/80 Safety Features Systems and for l
Normal Ventilation Systems B-63 (8045)
Isolation of low Pressure Systems All Plants NC NUREG 1031.
,4 Connected to the Reactor Coolant System Pressure Boundary t
i r
I 1
i f
Millstone Unit No. 3 1 i
[
- I.
Provide a separate entry for each licensed reactor unit.
If the information is identical for multiple units, so state.
2.
If a GSI is not applicable to a unit (s), enter "NA."
3.
If a GSI is applicable but no changes were necessary to implement the resolution, enter "NC."
If the GSI implementation was completed prior to issuance of the operating license, enter "NC," as no postlicensing changes were necessary.
4.
If a GTI is applicable, submittal of information and/or changes were necessary and such submittals were made or changes are complete, enter "C."
Also identify the licensee's document (s) to the NRC which certified completion, and the document date(s).
5.
If a GSI is applicable and changes are necessary but such changes are not yet fully implemented, enter "I" and the projected month and year of completion. Provide a brief explanation of the outstanding work in the " Comments" column.
73 6.
If implementation guidance for a resolved GSI was issued recently and the licensee is still evaluating j$
the appropriate response, enter "E" and the projected response date.
cu f3 7.
The " Comments" column may be used to explain any entry in the " Status" column.
l
,o NRC/NU Counterparts Meeting November 8, 1990 i
l III.B Plant-Specific Regulatory Issues
+
Page 48
NRC/NU Counterparts Meeting November 8, 1990 III.B Plant-Soecific Reaulatory Issues Millstone 1 Initiatives Recentiv Submitted 1.
ASME Section XI Relief Request--Valve Body Examinations 2.
ASME Section XI Relief Request--Hydrostatic Pressure Tests 3.
1.NP Logic Information 4.
Appendix J Exemption Request--Additional Information 5.
IST Program Update 6.
Generic Letter 90-05 on Non-ASME Code Repairs Vocomina Initiatives 1.
ISAP Topics Update Report 2.
Response to Generic Letter 89-10, Supplement 3 3.
Technical Specifications Requested by Generic Letter 88-01 SER 4.
Diesel Generator and Gas Turbine Generator Technical Specification Change (Surveillance Requirements) 5.
Diesel Generator Fuci Supply Technical Specification Change 6.
Response to NRC's Purce/ Vent Letter 7.
Hardened Vent Letter 8.
MCPR Safety Limit Technical Specification Change Lona-Term Initiatives 1.
Longer Fuel Cycles 2.
Removal of Containment Isolation Valves From Technical Specifications Page 49
NRC/NU Counterparts Meeting November 8, 1990
!!!.B Plant-Specific Reaulatory Issues (cont.)
Millstone 1 (cont.)
Lona-Term Initiatives (cont.)
3.
IPE Effort 4.
Containment Analysis 5.
GL 89-10--MOV Testing Awaitina NRC Action 1.
TMI Technical Specifications 2.
E0Ps 3.
ISAP License Condition Millstone 2 Initiatives Recentiv Submitted 1.
Core Operating Limits Report, Rev. O, Cycle 11, Submitted to NRC 2.
Generic Letter 87-09--Technical Specifications 3.
Information on Boraflex Degradation of SFP Rocks 4.
Information on Old Design CEA Inspection Results 5.
SB0 Safety Evaluation Response 6.
Request for Approval of Core Alteration Technical Specification 7.
GL 89-14 Technical Specifications / Removal of 3.25 Time Interval 8.
Generic Letter 90-05 on Non-ASME Code Repairs Page 50 t
NRC/NV Counterparts Meeting November 8, 1990-
!!!.B Plant-Soecific Reaulatory Issues (cont.)
Millstone 2 (cont.)
Vocomino Initiatives 1.
Fire Protection / Spray / Sprinkler /Halon System Technical Specifications 2.
Submittal to NRC on Recent S/G Inspection Results 3.
Response to Additional Questions on-Boraflex Issue 4.
Guidance on Seismicity Technical Specification Issue 5.
In-Service Testing-SER--Response 6.
CRDR Mods--Completion Letter 7.
JC0 on Auxiliary Steam System Lona-Term Initiatives 1.
PRA Development /ISAP Implementation /IPE Implementation 2.
Removal of Containment Isolation Valves From Technical Specifications 3.
Longer Fuel Cycles 4.
S/G Replacement 5.
Ultimate Heat Sink Study 6.
GL-89-10--MOV-Testing Awaitina NRC Actions RBCCW Appendix J Exemption Page 51
NRC/NV Counterparts Meeting November 8, 1990 III.B Plant-Soecific Regulatory Issues (cont.)
Millstone 3 Initiatives Recent1v Submitted 1.
Containment Pressure--Technical Specifications 2.
Electrical Power System--Technical Specification--
GL 84-15 3.
IPE Submittal 4.
RHR Autoclosure Interlock Deletion--GL 88-17 Recommendations e
5.
Cycle 4 Reload Submittal--Technical Specifications 6.
Generic Letter 90-05 on non-ASME Code Repairs 7.
Plant-Specific Simulator Certification Submittal Vocomina Initiatives 1.
Spent Fuel Pool--Technical Specifications 2.
Initial ISAP Submittal Lona-Term Initiatives 1.
Longer Fuel Cycles--1991 to 1992 2.
GL 89-10--MOV Testing Awaitina NRC Action None Page 52
i NRC/NU Counterparts Meeting November 8, 1990 III.B Plant-Soecific Reculatory Issues (cont.)
Haddam Neck Plant Initiatives Recentiv Submitted
,1.
Zircaloy Cladding Conversion / Appendix K Exemption Request 2.
September 28, 1990, ISAP Report--Six Month Update 3.
Appendix J--Changes to Permanent Exemptions 4..
Generic Letter 90-05 on Non-ASME Code Repairs Vocomina Initiatives 1..
Zircaloy Cladding Conversion / Proposed Technical Specification Changes, Large-Break LOCA Analysis 2.
Appendix A GDC Review of Containment Penetrations 3.
RCP Seal' Leakage 4..
Detailed CRDR:
Final Resolution Lona-Term Initiatives
- 1..
Zircaloy Cladding Conversion /W-Large Break LOCA
-Evaluation i
.2.
Tornado-Missiles Evaluation 3.
GL 89-10--M0V Testing 4.
IPE Efforts Awaitina NRC: Action 1.
License Amendment on 160 Failed Fuel Rod Limit i
2.
ISAP License Condition Page 53
-.- - ~
r
,e e
NRC/NU Counterparts Meeting November 8, 1990
~
III.C NRC/NU Interface on Selected Topics Page 54
f NRC/NU Counterparts Meeting November 8, 1990 III.C NRC/NU Interface on Selected Tooics How Can We Improve NRC/NU Communications / Interface?-
1.
Use of Industry-/NRC-Sponsored Technical Specification Improvement Initiatives a.
Core Alteration Definition for Millstone 2 (1)
NNECO Commitment to Revise Definition, Dated 4/3/89 (2)
NRC Inspection Report No. 89-05, Dated 5/4/89, Identified Issue as Unresolved iending Resolution of Planned Technical Specification Change (3)
Proposed -Technical Specification Change-i Submitted 4/10/90 (4)
Revised Proposed Technical Specification Change Submitted 6/26/90 l
(5)
Bases Changed Pursuant to 10CFR50.59 to Resolve Issue (6)
Recent NNECO Letter Dated 10/30/90 b.
Seismicity Technical Specification Change for Millstone 2 (1)
NNECO Submitted Proposed Technical Specification on 3/27/90 (2)
Subsequent Discussions With NRC Staff Resulted in Revised Proposed Technical Specification
-Submittal on 4/19/90 (3)- Informe'd Technical Specification Would Not Be Approved (4)' Alternative Solution Identified c.
Generic Implications (1)
Discuss NRC Position on Technical Specification Changes (2)
Optimize NRC/NV Resource Expenditures Page 55 l
is r
NRC/NU Counterparts Meeting November 8, 1990 III.C NRC/NU Interface on Selected Tooics (cont.)
i
- 2..
Use of ISAP Information 4
a.
Neutron Flux Monitoring System for BWRs (1)
Proposed Closure of ISAP Topic 1.09 in 8/4/87, 11/9/88, and 9/29/89 ISAP Reports (2)
On 2/13/90, the NRC requested Installation of Qualified Neutron Flux Monitoring Instrumentation Appeared to be-Generic Evaluation (3)
No Discussion of Millstone 1 Justificatt Closure (4)
Reevaluated in ISAP and Will be Discussed in 11/30/90 Report b.
Regulatory Guide 1.97 SER for Connecticut Yankee (1)
SER Issued 1/18/90 (2)
SER Did Not Address Items Previously Eval ated in ISAP and Proposed to Be Dropped in 11/23/87 and 3/2/89 ISAP Reports c.
Generic Implications.
(1)-
How Can NRC/NU Interface Be Improved to-Better.
Assure ISAP Information is Utilized by Staff.
When Addressing Generic Issues?-
(2)
Can a Mutually Agreeable ISAP Threshold for Dropping Topics Be Established?
l l
I I
i Page-56
NRC/NU Counterparts Meeting November 8, 1990 III.C NRC/NU Interface on Selected Topics (cont.)
3.
Generic Letter (GL) 90-05 on Non-ASME Code Repairs a.
Requested to Abide by a Draft Generic Letter Which Could Not Be Provided to NU b.
Documented NU's Approach on 4/20/90 c.
CRGR Chairman Advised NV That Draft GL Was Not to Be Issued (5/90) d.
GL 90-05 Issued on 6/15/90 e.
Several Relief Requests Submitted Pursuant to GL 90-05 NRC/NV Resources Expended Exceeded Safety Benefit Repairs Completed Unchanged by Documentation i
Process f.
NRC Staff's Position is Clarified in Millstone 2 Letter Dated 9/14/90 g.
NU Letter Dated 11/5/90 Docketed Our Understanding of Generic Applicability of Staff's 9/14/90 Letter h.
Additional NRC Feedback i.
Generic Implications (1)
Requests 1to Meet Draft NRC Documents (2)
NRC/NU Resource Expenditures More Commensurate With Safety Benefit (3)
Consistent Interpretations for All NU Plants I
Page 57
y..i-.-
NRC/NU Counterparts Meeting November 8, 1990 IV. OTHER REGULATORY ISSUES 4
Page 58
e NRC/NU Counterparts Meeting November 8, 1990 IV.C Midcycle SALP Page 59 1
SCHEDULE OF SALP ACTIVITIES BY MONTH FOR ONE SALP CYCLE SALP PERIODBEGNS 0-1 ON-SITE MID-CYCLE SALP
[gggg\\\\y 7 th REVIEWBYTHE F4tCSTAFF UCENSEE PRESENTATX)N 8 th TOTHE STAFF (REGIONI) 8 U
h\\M AN DNh\\D3hD M 8*
m e n s a w w w s e w is =
or e
O
'ecNsET-mmT ln$4%%\\%%%%%%%%%%%31 '8 '"
~
I M. N RB W RECB E g g gN g \\g g g g g g g g'g g g g g p m FIGURE 1
NRC/NU Counterparts Meeting November 8, 1990 o
LONG-RANGE INSPECTION SCHEDULE Page 61
s November 7, 1990 1990 NRC MEETINGS AND OTHER EVENTS OF INTEREST PAST EVENTS Jarauary 31 ~
Dr. Ivan Catton (ACRS) Visit February 1 rebruary 20 Enforcement conference -
Shipment of Contaminated Materia)s rebruary 22 Millstone 2 Steam Generator Meeting February 22 CY P, vent V rebruary 26-28 Atomic Energy Control Board of Canada (visit coordinated through the NRC)
Febryary 28 -
NRC/NUMARC Maintenance Meeting March 1 March 1 Millstone 2 EOPs March 5 Counterparts Meeting March 13 NU Reporting Philosophies and Processes March 19.,20,21 Mid-cycle SALP Inspection for Millstone 1 March 22 Nuclear Safety Concer.ns Program i
March 26 NUCLtNOR (3 pain) Personnel Vitit at Millstone 1 March 26 -
CY INPO Evaluation April 6 April 2-6 CY Erieryency Preparedness Inspection April 3-4 Two-day Mid-cycle SALP Inspection for ni11 stone 2 April 11, 12, CY INPO SGmulator Audit 18 and 19 April 16-27 Millstone 3 EOP Audit April 18 Mid-cycle SALP Inspection foi Millstone 3 April 20 NU 400 Club Heeting Page 62
i O
9 l
November 7, 1990 PAST EVERTT (Cont'd.)
April 23-25 Millstone 2 2 team Generator Inspection 1
April 24-26 NEO Team Building Co6ftrence May 1-2 NRC Regulatory Information Conference May 3 CY Pre-Exercise Rehearsal Drill
- May 8 Mid-cycle SALP Meeting for the Millstone site May 9 CY Action Plan for Re-statt and Fitness-for-puty May 10 CY SALP Meeting with NRC 11 Millstone 2 Steam Generator 73eting Hay 19 CY rull Participation Exercist May 21 CY Pressurizer Inspection May_22 Ghareholders Meeting Mar 23 Pi NRC Radiation Protection Managers' Cen'.t renae May 24 Millstone 1 Enforcement Confere'..ce May 14 CY fuel Reconstitution / Shutdown Equipment fo Cycle 16 June 4 Millstont: 3 NRC Training Effectiveness 0
Inspection June 4-8 Haddam Neck Plant Requalification Program Evaluation June 4-8 Millstono 3 NRC Accreditation Audit June 6 NRC Meeting in Berlin - 10CTR52, Standard ntsign certifications June 11 FM/DIF Meeting on seabrook u
June 11-'15 NRC In'pection on Engineering Support of l
Millstoae Page 63 i
l
... -a =,_,
~... _
.. _. _ _ _ _ _ _.. _ m _ _ _ ;._. _..
4 November 7, 1990 PAST EVENTS (Cont'd. )
June 13 ISAP/LRDR Meeting with NRC June 15 Enforcement conference on Radwaste Shipment June 18-22 Millstone 2 Requalificatirti Program Evaluation June 18-29 Second Round INPO Accreditation June 20-21 NUS Corporation LER Workshop,-King of Prussia, PA June 20-21 NRC - Utility Inspection Workshop June 25-20 NRC - 10CTR50.59 Audit at Millstone 3 June 25-29 NRC Region I Staff Inspection SALP runctional i
Area " Engineering Support" at Millstone June 27=
Nuclear Assurance Corp. Visit at CY and Millstone - Spent ruel Pool Transportation
-Routes June 28
-Second Counterparts Meeting July 9-13 NRC Inspection of Millstone 1 Radiological Environmental Monitoring Program (one week).
July 9-20 CY Start-up' Inspection (two weeks)
- July 11-EPRI Meeting at NUSCO - Risk Based Technical Specifications t
July 25 NRC Public Meeting near Millstone July 23-27 Millstone 3 - R.G. 1.97 Audit
-July 23 HP and Radiation Controls Inspection at Millstone site July _31 -
Inspection of Radwaste/Transportetion/ Shipping
- August: 1 at Millstone July 31 -
NRC Inspection on CY Reactor Coolant System Cycle Fatigue August 1 Operator Licensing Seminar - NRC Region I August 13 BWROG-LER Committee Meeting with the NRC Page 64
I November 7, 1990 PAST EVENTS (Cont'd.)
August 27-28 NRC Visit re Control Room Habitability for Millstone 1 and Connecticut Yankee August 27-31 Reactor Operator and Senior Reactor Operator License Examinations (one week)
September 5-6 Maintenance Standard Workshop September 10-14 Millstone 2 Allegations Team rollow-Up September 10-14 Millstone 3 NRC Inspection September 10-21 CY Maintenance Team Inspection (two weeks)
September 10-21 DOE Aerial Survey (Radiological) at Millstone Site September 10-14 Routine Safety Inspection at Millstone September 12-14 NUHARC ritness-for-Duty Workshop (Detroit, MI)
September 24-28 ritness-for-Duty Inspection and Audit a
September 25-28 Reportability and Operability Determinations Inspection - CY, Millstone, NUSCO October i NRC Backfitting Workshop in King of Prussia, PA October-2 NRC Event Reporting Workshop in King of Prussia, PA October 1-3 Millstone 1 LPCI NRC Inspection October 1-5 CY RG 1.97 NRC Audit October 1-5 Health Physics Audit at Millstone October 1-12 Nuclear Safety Concerns Program Inspection (two weeks)
October 9-17 CY NRC Inspection of Emergency Operating Procedures October 11-12 Commissioner Curtiss visit, October 11 at MP, October 12 at CY Page 65
l November 7, 1990 1
PAST EVENTS (Cont'd.)
October.15 NRC Meeting on CY Control Room Design Review in Bethesda, MD october 15-19 Emergency Preparedness Audit at Millstene October 16 Millstone 1 Degraded Grid Meeting with NRC in Washington October 16-17 Russian Delegation Visit to Haddam Neck and-Simulator racility October 22-NRC Fitness-for-Duty Enforcement Conference in King of Prussia, PA October 23 Rochester Gas & Electric Visit to Berlin Octobor Operator Requalification Exams at Millstone 3 November 2 UPCOMING EVENTS
-November.6-8 NRR Audit at Millstone 3 on GL 89-10, MOV
-Testing November '
Millstone 3 IPE Meeting in Washington, DC November 7 Millstone 1 LPCI Heat Exchanger Meeting November 7-8
. CY Mid-cycle SALP Inspection November 8 Third Counterparts Meeting in Berlin i
November 28 NEO Management Conference l November Southern California Edison visit to Berlin.
(tentative)
November CY. Radiological Effluents Inspection (tentative)
December 4 CY'- Corporate Support of Health Physics /ALARA, SSFI' Presentation, and
. Mid-cycle SALP11n King'of Prussia (tentative)
December 5 Millstone Partial Particiation Exercise December 13 Seabrook Station 1990 Biennial Exercise Page 66 v
v 3
--na 4
p
- w.
November 7, 1990 1991 UPCOMING EVENTS January 21 -
Haddam Neck Electrical Distribution System February 11 runctional Inspection rebruary 20-21 Region I Utility Symposium on Engineering's Role in Plant Support - King of Prussia, PA March-11-22 INPO E&A and Simulator Evaluation (tentative)
March 6 NUMARC Board of Directors Meeting -
"ashington, DC May CY Partial Participation Exercise (tentative)
Spring Visit to Millstone by CPU Board of Directors (tentative)
June 27 MUMARC Board of Directors Meating -
Washington, DC August -
Millstone 1 and 2 Electrical Distribution September System runctional Inspection October Millstone Full Participation Exercise (tentative)
November 20 NUMARC Board of Directors Meeting -
Washington, DC Page 67
,e i
NRC/NU Counterparts Meeting November 8, 1990 1
a V. SELECTED'NU INITIATIVES Page 68
NRC/NU Counterparts Meeting November 8, 1990 V.A Millstone 2 Steam Generator Replacement Package 1
Page 69
,4-MP2 Steam Generator Replacement Project - Hnndouts 1
D MILLSTONE 2 STEAM GENERATOR REPLACEMENT PROJECT NRC Presentation k-MP2 S/G REPLACEM NT PROJECT I
)
MP2 S/G REPLACEMENT p
I.
Overview II. Design & Operations Ill. Construction & Engineering IV. Summary V. Questions & Answers MP2 S/G REPLACEMENT PROJECT Page 70 i
L
MP2 Steam Gen @rator Replacement Project - Handouts 1
PROJECT BACKGROUND E Steam Generator Problems E System improvements E_ S/G Replacement Study E Procurement Of Spare S/G's E Formation Of Project Team MP2 S/G REPLACEMENT PROJECT
'b
SUMMARY
SCHEDULE 3
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SGRP SUPPORT FACILITIES E Project Offices At Site (completed)
E SGSA Storage & Fabrication Shop (12/90) 4 5 Mock-up & Training Facility (7/91)
E Containment Access Structure (12/91) m Craft Assembly Support Facility (12/91)
MP2 S/G REPLACEMENT PROJECT Page 72
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DESIGN & OPERABILITY CONSIDERATIONS E Project Milestones B Design improvements
- 1. Operations / Maintenance
- 2. ALARA B Related Project Activities MP2 S/G REPLACEENT PROJECT f
PROJECT MILESTONES Comoletion Date EPO For New S/G's Feb '88 Einstallation Contract Apr '90 R1990 Outage Oct '90 MNew S/G Delivery Apr '91 EEngineering Complete Sep '91 EReplacement Outage Sep '92 MP2 S/O REPLACEMENT PROJECT Page 74 1
MP2 Stoam Generator Replacement Profect - Handouts f
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DESIGN IMPROVEMENTS OPERATIONS / MAINTENANCE N Corrosive Resistant Materials W Bundle Design R Improved Chemistry Controls B increased Access Openings N Nozzle Dams W ECT Inspectability MP2 S/G REPLACE T PROJECT DESIGN IMPROVEMENTS ALARA E Material Selection & Preparation E increased Access Opanings E Nozzle Dams E Staging & Shielding Mods MP2 S/G REP EMENT PROJECT Page 75
MP2 Steam Gonorator Replacement Profect - Handouts
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RELATED PROJECT ACTIVITIES E Wet Layup Recirculation 5 Staging Modifications E Wide Range LevelIndication E Dryers & Separator Mods E MS Flow Restrictor l
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REPLACEMENT METHOD E Upgrade Polar Crane E Structural Mods E Fuel Pool Cover
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1990 OUTAGE WORK ACTIVITIES E
Construction Trolley installation E Containment SteelInstallation L
E Measurements Of Steam Drum Internals E Photogrammetry Of RCS E Engineering "'alkdowns s
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MP2 Steam Gen @rator Replacement Project - Handouts 1
LICENSING B
Safety Evaluations Have Been Started.
E To Date, No Unreviewed Safety Questions.
E NU's Preliminary Assessment:
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REPLACEMENT PHILOSOPHY B
Lessons Learned From S/G Replacements E
State Of-The-Art Technology B Personnel Exposure B
Pre-Replacement Training B
Contingency Planning
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CONCLUSION E Quality First E Detailed Planning 5 Open Communication With hRC E World Class Replacement MP2 S/G REPLACEM NT PROJECT Page 80
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NRC/NU Counterparts Meeting November 8, 1990 V.B - Millstone 1 Future Technical Specification Changes Page 81
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- NRC/NUTCounterpartsl Meeting November-8, 1990 LV.B: Millstone 1 Future Technical Soecification Chanaes 1.
Reasonsifor Initiating Effort
-a,
= Review of Technical Specifications for' Consistency and Implied Values Performed Because of Gas Turbine
-Surveillance?NOV Response Commitment b.
NRC-Resident _ Inspector Concerns and. Questions Regarding Wording and Requirements c.
Initiation of a New Set Point-Program to Determine Technical Specification Specified ECCS, RPS, Etc.,
Set Points.
.c d.
Make-the ECCSESection.(3/4.5) Consistent With the New LOCA Analyses e.-
Plant Request for Separate Refuel Condition Section-That Brings All Refueling Related Requirements 1
1Together 1
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Page 82
NRC/NU Counterparts Meeting November 8, 1990 V.B Millstone 1 Future Technical Soecification Chanaes (Cont.)
2.
Program Approach a.
Three-Phase Program to Rewrite Technical Specification and Bases.
(1)
Technical Specifications to Be Written In Industry Standard Type Format (2)
Bases Written to Be Consistent With Improved Technical Specifications Philosophy b.
Phase I c.
Phase II d.
Phase III e.
Other Sections Page 83
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V.B. LMi11 stone 1 Future Technical Soecification Chanaes (Cont.)
3.
Program Schedule
- a.
Phase I--Submittal During First. Quarter 1991 b.
Phase:II--Submittal During Third: Quarter 1991 (Contingent Upon NRC Approval of= Phase I)..
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Phase III--Submittal During Third Quarter 1992
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NRC/NU Counterparts Meeting November 8, 1990 V.B Millstone 1 Future Technical Soecification Chanaes (Cont.)
Table 1 1.
Phase I a.
Cleanup Mode Definition b.
Rewrite and Reformat (1) 3/4.5 (2) 3/4.9 (3) 3/4.10 (4) 3/4.14 (5)
Selected Section of 3/4.6 and 7 (6)
Associated Bases 2.
Phase II a.
To be done following NRC Issuance of Phase I Changes b.
Rewrite and Reformat (1) 3/4.3 (2) 3/4.4 (3) 3/4.6 and 7 (Sections Not Done in Phase I)
(4) 3/4.12 (5) 3/4.13 (6)
Associated Bases l
Page 85
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,4 NRC/NU Counterparts Meeting November 8, 1990 V.B Millstone 1 Future Technical Soecification Chances (Cont.)
Table 1 (Cont.)
3.
Phase III a.
To Be Done Following:
(1)
NRC Issuance of Phase II Changes (2)
Completion of I&C Set Point Evaluation (3)
Completion of Any Safety Analyses Deemed Necessary Due to Set Point Changes b.
Rewrite and Reformat (1)
Definitions (Section I.0)
(2)
Section 2.0 (3) 3/4.1 (4)
Associated Bases 4.
Other Sections a.
3/4.8 Already Written in New Format b.
3/4.11 Rewritten as Part of Cycle 14 Reload Effort Page 86
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NRC/NU Counterparts Meeting-November 8, 1990 1
VI.
SUMMARY
AND CONCLUSIONS Page 87
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O NRC/NU Counterparts Meeting November 8, 1990 VI.
SUMMARY
AND CONCLUSIONS.
1.
NRC Feedback and Observations 2.
Future Meetings i
Page 88