ML20133P934

Informs That Completion of Integrated Safety Assessment Scheduled for Sept 1985 for Millstone Unit 1 & Sept 1986 for Haddam Neck.Projects Listed in Encl Should Be Conducted Independent of Integrated Safety Assessment Program

ML20133P934
Person / Time
Site:	Millstone, Haddam Neck, 05000000
Issue date:	07/31/1985
From:	Thompson H Office of Nuclear Reactor Regulation
To:	Opeka J NORTHEAST UTILITIES
References
TAC-56906, NUDOCS 8508140540
Download: ML20133P934 (14)

Text

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f[ A'g UNITED STATES NUCLEAR REGULATORY COMMISSION n ;j WASHINGTON, D. C. 20$55

\ *~* / JUL 311985 Docket Nos.: 50-213 and 50-245

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Mr. John F. Opeka, Senior Vice President Nuclear Engineering and Operations Northeast Utilities Post Office Box 270 .

Hartford, Connecticut 06141-0270

SUBJECT:

INTEGRATED SAFETY ASSESSMENT PROGRAM In your letter date'd May 17, 1985, Northeast Utilities outlined a proposal for the conduct of the Integrated Safety Assessment Program (ISAP) for the Haddam Neck and Millstone Unit I facilities. Your proposal generally described the procedures for the conduct of this effort and specifically identified (1) those projects which would be conducted independent of ISAP, including plant modifications which will be implemented during the next refueling outage for each facility and ongoing ("baseload") engineering studies, and (2) those licensing matters and NNEC0/CYAPC0 plant improvement projects which should be evaluated in an integrated assessment for each facility.

Your proposal also described the criteria you would use to evaluate each of the issues in the integrated assessment and subsequently prioritize the corrective action resulting from the integrated assessment.

The NRC has allocated resources for the conduct of ISAP for Haddam Neck and Millstone Unit 1. Based on the availability of the probabilistic safety analysis (PSA) results, and in consideration of the refueling outage schedules, we have scheduled completion of the integrated assessment (i.e., draft report) for Millstone Unit 1 in September 1985, and Haddam Neck in September 1986. We believe that these schedules are achievable and will ensure efficient use of both NRC and NNEC0/CYAPC0 resources.

The staff has concluded that the projects for each facility listed in Enclosure 1 to this letter should be conducted independent of ISAP. These projects include (1) plant modifications and procedural changes that are ready for implementation during the next scheduled refueling outage or before the scheduled completion of ISAP and/or are significant safety improvements that should not be delayed, and (2) ongoing engineering studies and plant modification design efforts that have a well defined objective and would not likely be enhanced by an integrated assessment.

8508140540 850731 PDR ADOCK 05000213 P PDR

Mr. John F. Opeka Enclosure 2 to this letter identifies those projects for each facility that we believe should be evaluated in ISAP. These projects have been numbered for ease of reference and accountability. The first group of projects includes all current licensing actions and plant activities, and also includes pending and potential licensing requirements. The second group includes NNEC0/CYAPC0 initiatives and plant improvements. We have added to the projects you proposed:

(1) the pending licensin is not yet complete; (2)g actions from NUREG-0748 the NNEC0/CYAPC0 for which the ongoing engineering staff's studies review

("baseload")

that we believe should be evaluated, at least in a broad sense, for their potential contribution to plant safety; and (3) those Unresolved Safety Issues and generic issues, derived from the high-priority issues in NUREG-0933, that we believe can be substantially addressed on a plant-specific basis in concert with the PSA for each facility. These projects comprise the " topics" for evaluation under ISAP. The staff considers the scope of review represented by these topics, in conjunction with the PSA evaluations and updated operating experience evaluations, to be sufficiently comprehensive, such that the results of the integrated assessment will provide effective integrated schedules and the basis for future regulatory actions.

The tables presented in Enclosure 2 identify those topics for which you identified specific deterministic or probabilistic evaluations to support the integrated assessment. A number of your proposed topics identify specific plant improve-ments for the purpose of prioritization; however, it would appear that more effective or efficient alternatives may evolve from the integrated assessment by evaluating the original motivation for these plant improvements. In order to ensure that the issues to be addressed in the integrated assessment are clearly defined and understood, we request that evaluations be prepared in the following fomats:

1. All of the topics for which safety analyses have already been submitted to the NRC and no further NNEC0/CYAPC0 analysis is considered necessary should be clearly identified. While we have identified some references of this nature in your May 17, 1985 submittal, we believe it would be useful for you to sumarize these topics in tabular fom, noting the dates of your submittals and any related staff evaluations. We are currently assembling this material and will use your tabular sumary to ensure that all of the pertinent documentation has been identified.

2. All of the topics for which NNEC0/CYAPC0 safety analysis are or will be performed should be submitted in the format specified in your May 17, 1985 letter. For Haddam Neck, we request that you provide the submittal schedules so that we may plan our review; all of these analyses should be submitted by about June 1986.

3. For all of the other topics, which consist primarily of the NNEC0/CYAPC0 plant improvement projects, we request that you submit a concise sumary of each topic which identifies the fundamental concern being a'ddressed, advantages and disadvantages of any proposed corrective action relative to the attributes described in your May 17, 1985 letter, and plant design features pertinent to the issue. These summaries may be submitted indi-vidually or collectively.

. I l

John F. Opeka i

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4. For each of the topics that will be addressed with a specific PSA '

evaluation, a sumary of the PSA finding should be submitted which includes:

(1 the issues being addressed, (2) any corrective actions considered, (3 the affected systems, (4) a description of the analysis performed, (5 the associated fault tree (s), (6) the analysis assumptions, and  !

(7 the conclusion. These sumaries may also be submitted individually or collectively.

The staff will review these submittals and issue safety evaluation reports which will identify the specific issues to be addressed in the integrated assessment.

The topics identified in Enclosure 2 include all pending licensing actions and ongoing engineering studies, some of which are nearly complete. Consequently, should you identify topics during the course of the review that are resolved or change in scope, please notify us.

Similarly, because of the ISAP review schedule for Haddam Neck relative to the plant's refueling outage schedules, it is apparent that a substantial amount of engineering and procurement for the Spring 1987 outage will have to be accomplished before the integrated assessment is complete. We encourage you to schedule the Haddam Neck topic analyses so that significant safety improve-ments can be developed for implementation in the Spring 1987 outage. As you identify such implementation plans, you should notify us so the scope of the related topic reviews may be adjusted accordingly.

Because of the schedule and resource constraints, the staff's review of the PSA for each facility will be limited to an audit of your analyses. The staff and consultants assigned to this effort are currently reviewing the Millstone Unit 1 IREP results and the material presented in a meeting held on June 3,1985, to prepare for this audit. The objectives of the staff's review will be to judge whether (1) the appropriate contributors to risk have been identified for consideration in the integrated assessment, and (2) the conclusions presented for each topic analysis are appropriate. In view of the schedule constraints for Millstone Unit 1, we request that the topic-specific analyses be submitted as soon as practical. We will organize the Haddam Neck review later in the year when the analyses for that facility are nearing completion.

With respect to the attributes you have proposed as prioritization criteria, we do not intend to review all of these criteria and the ranking procedures in detail. Rather, we will evaluate your assessment of the impacts on public health and safety for each topic and subsequently judge the overall integrated implementation schedules proposed based on those conclusions.

As a result of the staff's screening review of topics to be addressed in ISAP, we note that there are a few issues that may require exemptions or . license amendments to defer action until ISAP is complete. In accordance with the required procedural practices, you should separately request the necessary exemptions or license amendments to defer these requirements. We will act on such requests promptly. Your requests for deferrals or exemptions should

. July 31,1985 0

John F'. Opeka clearly state the justification for continued plant operation and compensatory plant design features which form the basis by which you have concluded that the issue involved may be deferred until a more effective resolution and implementation schedule can be developed from the integrated assessment.

For example, your May 17, 1985 submittal indicates that you intend to complete all of the inadequate core cooling instrumentation (ICCI) for Haddam Neck during the 1986 refueling outage; however, you have proposed a concurrent evaluation of the need for a heated junction thermocouple system (Topic 1.13). If you decide to defer completion of ICCI, you should notify the staff promptly and include a detailed explanation of the technical basis by which you have concluded that issue can be deferred.

New issues that arise during the course of this review will be evaluated for inclusion in ISAP in the following manner: Issues raised by the staff on a plant-specific basis will be reviewed for safety significance. If prompt action is deemed necessary, we will request such action in accordance with 10 CFR 50.54(f). Otherwise, we will forward the issue for your evaluation and note the assigned ISAP topic number. Issues raised generically, including new regulations, generic letters and IE Bulletin follow-up actions should be evaluated by NNEC0/CYAPC0 and, if you conclude the matter should be addressed in ISAP, a deferral should be formally requested. We will respond to such requests promptly and, if they involve exemptions, the deferral request will be evaluated in accordance with 10 CFR 50.12, as described above.

This letter concludes the staff's screening review of topics to be addressed in ISAP for Haddam Neck and Millstone Unit 1. In order for us to expeditiously proceed with this effort on Millstone 1, we request that you promptly provide the analyses discussed above. For Haddam Neck, we request that you provide submittal ~ schedules and identify where specific probabilistic analyses will be conducted, based on your preliminary planning. Should you have any questions concerning this matter, please contact Christopher Grimes, (301) 492-8414 Or'ginal signed by: Hugh Thompson Hugh L. Thompson, Jr., Director Division of Licensing Office of Nuclear Reactor Regulation

Enclosures:

DISTRIBUTION TSpeis PDR LPDR As stated , Central File r JShea MBoyle HThompson/FMiraglia JZwolinski FRowsome cc: See next page CGrimes AThadani FAkstulewicz

• PREVIOUS CONCURRENCE SEE DATE SEPB:DL* SEPB:DL* ORB #5:DL* ORB #5:DL* ORB #5:DL*

MBoyle:mn CGrimes FAkstulewicz JShea JZwolinski 7/01/85 7/01/85 7/08/85 7/03/85 7/03/85 AD:SA:DL* RRAB: DST

• RRAB: DST

• D: DST

• REGION I*

DCrutchfield AThadani FRowsome TSpeis EMcCabe 7/08/85 7/19/85 7/19/85 7/19/85 7/03/85 o

Hh 7/y/35

I t

John F'. Opeka clearly state the justification for continued plant operation and compensatory plant design features which form the basis by which you have concluded that the issue involved may be deferred until a more effective resolution and implementation schedule can be developed from the integrated assessment.

For example, your May 17, 1985 submittal indicates that you intend to complete all of the inadequate core cooling instrumentation (ICCI) for Haddam Neck during the 1986 refueling outage; however, you have proposed a concurrent evaluation of the need for a heated junction thermocouple system (Topic 1.13). If you decide to defer completion of ICCI, you should notify the staff promptly and include a detailed explanation of the technical basis by which you have concluded that issue can be deferred.

New issues that arise during the course of this review will be evaluated for inclusion in ISAP in the following manner: Issues raised by the staff on a plant-specific basis will be reviewed for safety significance. If prompt action is deemed necessary, we will request such action in accordance with 10 CFR 50.54(f). Otherwise, we will forward the issue for your evaluation and note the assigned ISAP topic number. Issues raised generically, including new regulations, generic letters and IE Bulletin follow-up actions should be evaluated by NNEC0/CYAPC0 and, if you conclude the matter should be addressed in ISAP, a deferral should be formally requested. We will respond to such requests promptly and, if they involve exemptions, the deferral request will be evaluated in accordance with 10 CFR 50.12, as described above.

This letter concludes the staff's screening review of topics to be addressed in ISAP for Haddam Neck and Millstone Unit 1. In order for us to expeditiously proceed with this effort on Millstone 1, we request that you promptly provide the analyses discussed above. For Haddam Neck, we request that you provide submittal schedules and identify where specific probabilistic analyses will be conducted, based on your preliminary planning. Should you have any questions concerning this matter, please contact Christopher Grimes, Chief of the Integrated Safety Assessment Branch on (301) 492-8414.

Hugh L. Thompson, Jr., Director Division of Licensing Office of Nuclear Reactor Regulation

Enclosures:

DISTRIBUTION TSpeis As stated Central File JShea MBoyle HThompson/FMiraglia JZwolinski FRowsome cc: -See next page CGrimes AThadani FAkstulewicz

• PREVIOUS CONCURRENCE SEE DATE SEPB:DL* SEPD:DL* ORB #5:DL* ORB #5:DL* ORB #5:DL*

MBoyle:mn CGrines FAkstulewicz JShea JZwolinski 7/01/85 7/01/85 7/08/85 7/03/85 7/03/85 AD:SA:DL* RRAB: DST

• RRAB: DST

• D: DST

• REGION I*

DCrutchfield AThadani FRowsome TSpeis EMcCabe 7/08/85 7/19/85 7/19/85 7/19/85 7/03/85 D :DL l HThompson 7/ /85 L_

John F. Opeka This letter concludes the staff's screening review of topics to be addressed in ISAP for Haddam Neck and Millstone Unit 1. In order for us to expeditiously proceed with this effort, we request that you promptly provide the schedules and analyses discussed above. In particular, we request that, based on the topic sets as set forth in this letter, you identify the format for the deterministic analysis and whether a specific analysis is intended for each of the topics within ten days following your receipt of this letter. Should you have any questions concerning this matter, please contact Christopher Grimes, Chief of the Integrated Safety Assessment Branch on (301) 492-8414.

Hugh L. Thompson, Jr. , Director Division of Licensing Office of Nuclear Reactor Regulation

Enclosures:

As stated t

cc: See next page DISTRIBUTION Central File HThompson/FMiraglia CGrimes MBoyle FAkstulewicz JSHea JZwolinski AThadani FRowsome TSpeis

• PREVIOUS CONCURRENCE SEE DATE SEPB:DL* SEPB:DL* ORB #5:DL* ORB #5:DL* ORB #5:DL*

MBoyle:mn CGrimes FAkstulewicz JS JZwolinski 7/\/85 7/\/ 7 /3/ 7/3/85 AD:SA:DL* RRAB: DST RR  : DST D: T REGION I*

DCrptchfield AThadani Frow me tsp s EMcCabe 7/ %/85- 7/['/85 24f 5 85 7/S/85 1

D:DL L HThompson Yy[)[9 Y

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i ,

o John F. Opeka ..

This letter concludes the staff's screering review of topics to be addressed in ISAP for Haddam Neck and Millstone Unit 1. In order for us to expeditiously proceed with this effort, we request that you promptly provide the schedules and analyses discussed above. In particular, we request that, based on the topic sets as set forth in this letter, you identify the format for the deterministic analysis and whether a specific analysis is intended for each of the topics within ten days following your receipt of this letter. Should you have any questions concerning this matter, please contact Christopher Grimes, Chief of the Integrated Safety Assessment Branch on (301) 492-8414.

Harold R. Denton, Director Office of Nuclear Reactor Regulation

Enclosures:

As stated cc: See page 6 SEPB:DL MBoyle:

SEPB:DL CGrimes ORB #5:D: hORB #5:D FAkstulbwicz JShea s g ORB #5:DL JZwolinski 7/l/85 7/t/85 7/6/85 7/5/89 7/4,/85 0-A X/ RRAB: DST RRAB: DST D: DST REGION I y D ifield AThadani FRowsome TSpeis E.Mc Ccbc" 7/ /85 7/ /85 '7/ /85 7/ /85 7/ S /85 D:DL RR !

HThompson H (ton 7/ /85 -/Q

• concurecd % phone de Ergd o I

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. l Mr. John F. Opeka Haddan Neck Plant &

Connecticut Yankee Atomic Power Company Millstone Nuclear Power Station, Northeast Nuclear Energy Company Unit No. 1 I CC Gerald Gar #iald, Esauire Kevin McCarthy, Director Day, Berry 8 Hevard Radiation Control Unit  !

Counselors at Law Department of Enyironmental  !

City Place Protection Hartford, Connecticut 06103-3499 State Office Building Hartford, Connecticut 06!06 Edward J. Mroczka Vice President, fluclear Operations Board of Selectmen Nortbeest l'tilities Service Company Town Hall Post Office Box 270 Haddam, Connecticut 06103 Hartford, Cennecticut 06141 Superintendent State of Connecticut Haddam Neck Plant O'# ice of Policy and Management RFD #1 ATTN: Under Secretary Energy Post Office Box 127E Division - East Hampton, Connecticut 06424 80 Feshington Street Hartford, Connecticut 06106 Resident Inspector Heddan Neck Plant Regional Administrator c/o U.S. NPC Nuclear Regulatory Commission, Pepion I East Haddam Post Office 631 Park Avenue East Haddam, Connecticut 06423 King of Prussia, Pennsylvania 19406 Northeast Nuclear Energy Company ATTN: Superintendent Millstone Nuclear Power Station P. O. Fox 128 Waterford, Connecticut 06358 Resident Inspector c/o U.S. NP.C Millstone Nuclear Power Station P. O. Box 811 Niantic, Connecticut 06257 First Selectman nf the Tovn of Waterford Hall of Records 200 Boston Post Pced Waterford, Connecticut 063P5 9

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ENCLOSURE 1 COIPLETION OR ONG0ING PROJECTS INDEPENDENT OF ISAP Haddam Neck 1 Emergency Diesel Generator Trip and Lockout 2 Process Computer UPS Installation 3 Inadequate Core Cooling Instrumentation 4 EQ of Electrical Equipment 5 RCS Loop RTD Replacements 6 Seismic Qualification of Safety Related Piping 7 Plant Paging System Upgrade 8 M0V Thennal Overload Modifications 9 Appendix R Modifications 10 Refuel Cavity Drain Piping Seismic Upgrade 11 Reactor Cavity Seal Ring Modifications 12 Replace Main Control Board Cat. IE Relays 13 Feedwater Heater Modification 14 Steam Generator Wet Layup Recirculation 15 Review of Existing Control Air Systems 16 Doc. and Coord. of Protective Relay and Breaker 17 Replace Main Generator Neutral Grounding Trans.

18 Rev. and Upgrade Eval. for Diesel Air Start System 19 Waterbox "A" Retubing 20 Steam Generator Manway Cover Handling Device 21 Limitorque Motor Operated Valves-Lubrication 22 Elevated Well Water Temperature 23 RCCA Changeout Tool 24 Emergency Plan Rad. Assessment Equipment 25 Microwave System 26 Conversion to Standard Technical Specifications 27 Plant Design Change Task Group Support 28* Plant Training Simulator 29* Probabilistic Safety Study

• 30* Unit Availability Model 31* Computer Analysis for Generation of Heatup/Cooldown Curves k

ENCLOSURE 1 (continued)

Millstone 1 1 Seismic Qualification of Safety Related Piping 2 Primary Containment Leak Rate Monitoring 3 Undervoltage Protection-Emergency Bus 4 Replacement of Motor Operated Valvas 5 Floodgate Mode. and Installation of Scuppers 6 Refueling Cavity Seal Evaluation 7 Records Vault Temperature and Humidity Control 8 Process Computer UPS Installation "

9 MS Relief Valve Vacuum Breaker Load Qualification 10 Station Battery "A" Replacement 11 Rev. and _ Upgrade Eval, for Diesel Air Start System 12 Gas Turbine Generator Elec. Equipment Protection 13 Auxiliary Equipment System Oscillograph 14 Supervisory and Events Recorder Systems 15 Replace Main Generator Neutral Grounding Trans.

16 Limitorque Motor Operated Valves: Lubrication 17 460 Volt Motor Soft Start Capability 18 IGSCC Countermeasures 19 Circulating Water Piping Thrust Block Repairs 20 Gas Turbine Generator Battery Replacement 21 Solid Radwaste Building Ventilation and Roof Mods 22 Spent Fuel Pool Cleanup 23 Voltage Regulator, Instrument Trans Replacements 24 House Heating Boiler Stack 25 Procurement of Nuclear Grade Material / Service Sensitive Lines 26* Plant Training Simulator 27* Probabilistic Safety Study 28* Unit Availability Model 29* Roof Replacement 30 Emergency Gas Turbine Generator Vibration Switches

• Ongoing activities that represent a level of effort that must be maintained.

r ENCLOSURE 2

- Haddas Neck ISAP !ssues t

ISAP G Title - NRC lssues to be included in ISAP Source Cross Refernece Action Letters Sun PSA Notes

, _ , , ._ 4 .+ + .. , + ,+-+ +-+ +___,

1.01 Switchgear Room tooling Modifications SEP 11-5 TIA 83-89 04/05/84D Y 1.02 High/Los Pressure Valve laterlocks SEP V-11.A TIA B3-89 04/05/84D Y 1.03 Containment Penetration Evaluations SEP VI-4 50935;0660:ll.E.4.3 Y  !

1.0A Seisaic Qualification of Safety Related Piping SEP !!!-6 51937,51939;USI A-40 04/05/84D 3 1.05 Seissic Structural Modifications SEP III-6 51937,51939;USl A-40 04/05/84D 1.06 Wind and Tornado Loadings / Tornado Missiles SEP 111-26-4.A 51938,51939 Y 1.07 Vital Bus Feed Realignaent Modifications SEP VI-7.C.1 51934;TIA 83-89 1.08 Seisaic Modifications to Reactor Coolant Systes SEP 111-6 51937,51939;US! A-40 04/05/84D 1.09 Design Codes, Design Criteria, Load Combinations SEP 111-7.B 51939 Y 1.10 Torque Seitch Modifications SEP III-10 A Y 1.11 PAB Ventilation Systes Modifications SEP II-5 Y 1.12 Control Roos Habitability 0737:11.B.3.4 56320 04/05/84D Y 1 1.13 Inadequate Core Cooling Instrueentation 0737:!I.F.2 45138 Y 4 1.14 Appendia R Modifications 50.48 1.15 FDSA Update 50.71 04/11/85E 1 1.16 Anticipated Transients Without Scras ATUS USl A-9 1 1.17 Replacement of Motor Operated Valves' 50.49 42521,52074;US! A-24 04/05/84D;03/28/85E 1,5 1.18 RCP Seal Cooling Modifications - 0737:11.K.3.25 61-23 1.19 Control Roca Design Revien 0737:Supp! 1 56128,51165 1.20 Safety Paraseter Display Systes 0737:Supp! 1 51245 1.21 R6 1.97 Instrumentation 0737: Suppl 1 51095,45949,etc 1.22 Energency Response Facilities Instrumentation 0737: Suppl 1 51095 1.23 Post-Accidient Hydrogen Monitor (RS 1.97) 0737: Suppl 1 47745,49852;US! A-48 Y 1.24 TS Surveillance for Hydraulic Snubbers MTA B-17 08465 2 1.25 TS Surveillance for Mechanical Snubbers MPA B-22 08469 2 1.26 RV and SV Testing MPA F-14 44585 1.27 Compliance eith 50.46 (ECCS) 0737:ll.K.3.31 48169;MPA F-58 1.28 RCP Trip MPA 6-01 49667 1.29 Flooding Evaluation SEP III-3.C 51932 1.30 RPS Isolation SEP 51933 1.31 Pipe Breats SEP 51936 1.32 Ites 2.1-Equipsent Classification / Vendor Inter. Sales ATUS 52043 1.33 Itees 3.1.ll.2-Post Maintenance Testing Sales ATMS 52924 1.34 Ites 3.1.3-Post Maintenance Testing TS Changes Sales ATUS 53005 1.35 Reactor Trip Systes Reliability-Vendor Sales ATWS 53073 1.36 Ites 2.2-Facip. Classification / Vendor Interface Sales ATUS 53677 1.37 Itees 3.2.ll.2-Post Mainten. Testing Procedures Sales ATWS 53760 1.38 Ites 3.2.3-Post Maintenance Testing Changes to TS Sales ATWS 53843 1.39 Ites 4.2.38.4-Prev. Mainten. Proc. for Rx Trip Sales ATUS 53913 1.40 Itees 4.5.26.3-R Trip Systes Functional Testing Sales ATVS 53987 1.41 Ites 4.5.1-Reactor Systes Function Testing Sales ATWS 54070 1.42 RCS Vents TS 0737: 54393 1.43 TS fros 6L 83-36 & 83-37 MPA B-83 54538 1.44 Diesel Generator Reliability MPA D-19 55864 1.45 ISI Update to 1980 Code 56502 1.46 IST for Diesel Generator Auxiliaries 56917 1,47 Reliability Engineering NURE6-0933 0660:ll.C.2 1.48 Seisait Oualification of Equipment NURE6-0933 USI A-46 1.49 Steaa Generator Tube Integrity NURES-0933 USI A-3 1.50 Fracture Toughness of Supports NURE6-0933 USI A-12

r ENCLOSURE 2

, Haddas Neck ISAP !ssues ISAP I Title - NRC !ssues to be included in ! SAP Source Cross Refernece Action Letters Sue PSA Notes

+-++ ++ ++ ++~ + +-+ +-+ +---+

1.51 Systens Interactions NURE6-0933 USI A-17 1.52 Pressure Transient Protection NURE6-0933 USI A-26 1.53 Containment Energency Susp Performance NURES-0933 USI A-43 1.54 Safety !aplications of Control Systees NURES-0933 USI A-47 1,55 Radiation Protection Plans NURES-0933 0660:II.D.3.1 1.56 Bolting Degradation NURE6-0933 61-29 1.57 Flooding of Safety Equipment by Backflow NURE6-0933 61-77 1.58 Steam linding of Auxiliary Feed Pumps NURES-0933 61-93 ISAP I Title - NU !ssues to be included in ISAP Source Cross Refernece Action Letters Sua PSA Notes

+-++ + ++ + + +-+ +-+ +---+

2.01 Secondary Side Chesistry Monitoring ( NU MPAA-3 6L 85-02 Y

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2.02 DNST Oxygen Reduction NU MPA A-3 6L 85-02 Y 2.03 Additional Atmospheric Steas Dusp NU 2.04 Modernire Reactor Protection & Control Systess MU 2.05 Process Cosputer Replacement NU ISAP 1.20;51245 2.06 Eval, of RCS Loop Iso. Valves to Mitigate S6Tk NU US! A-3;ISAP 2.01,2,3 2.07 Auxiliary Pressurizer Spray Norrle NU 2.08 Loss of DC Power NU USI A-44; TAP A-30,8-56 2.09 RCP Vibration Monitoring Systes Upgrade NU 2.10 Administration Building Upgrade N!!

2.!! Main Steae Systes Evaluation NU 2.12 Turbine-Generator Trip Logic NU USI A-44 ttest

1. An exemption or license asendaent say be required.

2. May be resolved by implementation of the Standard Technical Specifications.

'3. To date 180 of the approrisately 450 pipe racks and supports have been modified.The licensee irtends to modify 8 pipe racks and 90 pipe supports inside containment and 31 pipe supports in the primary auxiliary building during then 1986 refueling outage. The remaining work l

is to be included in ISAP.

4. The licensee intends to implement all of the ICCI sodifications during then 1986 refueling outage unless a sore effective alternative for the heated-junction thersoccuple can be developed from the PSA.

5. The licensee plans to complete all of the envoronmental qualification of .

electrical equipaent according to the 10CFR50.49 schedule requirements, except for the notor operators for the 14 safety related MOVs. Before these notor operators can be installed, their effect on other ongoing projects, such is the seismic analyses, need to be evaluated.

f.

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- . 3 p Millstone 1 ISAP !ssues g ISAP I Title - NRC !ssues to be included in ISAP Source CrossRefernete Action Letters Sue PSA Nctes e.----+ +--- - - - - -

++ ++ + - -+ +.+ +-+ +---+

1.01 Bas Turbine Generator Start Logic Modifications SEP Vill-2 USI A-44;MPA D-19 04/05/84D Y A 1.02 Tornado Missile Protection SEP III-4.A 04/05/840 Y A 1.03 Containment Isclation-Appendix A Modifications SEP VI-4 1 1.04 RWCU Systes Fressure Interlock SEP V-l!.A 49380 04/05/84D Y A 1.05 Ventilation Systen Modifications SEP 11-5 Y A 1.06 Seisaic Qualification of Safety Related Piping IEB 79-02&-14 49379;IR 85-04 04/05/84D Y B 2 1.07 Centrol Roce Design Review 0737: Suppl 1 51176,56138 1.08 Safety Paraseter Display Systes 0737:Supp! ! 51256;! SAP 2.03 1.09 RS 1.97 Instruser.tation 0737: Suppl ! 51106;USI A-9 Y 1.10 Energency Res; case Facilities Instrumentation 0737: Suppl ! 51106;USI A-9 1.11 Post Accider.t Hydrogen Monitor 0737: Suppl 1 47754;USI A-48 Y 1.12 Centrol Root Habitability 0737:111.D.3.4 56319 04/05/84D B 1 1.13 BER Vessel Water Level Instrumentation 0737:ll.F.2 03/26/85 B 1.14 A;pendix J Mcdifications 10CFR50 Y 1 1.15 FSAR Update 50.71 04/11/85E;03/28/85E 1 1.16 Appendix R 50.48 48664 Y l

.1 MPl/MP2 Eackfeed A

.2 Mcdify CRD Pusps B

.3 Alternative Ecoling for Shutdown Cooling A

.4 Power Cold Shutdown Equipeent B 1.17 Replacement of M: tor Operated Valves 50.49 42523;USI A-24 04/05/84D l B 1,3 1.18 ATWS 50.62 56840 A 1.19 Integrated Structural Ananysis SEP 49376 1.20 MOV Interlecks SEP !!!-10.A 49380 -

1.21 FaultTransfers SEP VI-7.C.1 49384 A 1.22 Electrical Isolation SEP VII-1.A 49385 1.23 Erid Separaticn Procedures - SEP VI!!-1.A 49386 1.24 Energency Power SEP VIII-2 49387 1.25 De;raded Grid Voltage Procedures 51702 1.26 Ites 2.!-Ecuitsett Classification / Vendor Inter. Sales ATWS 52854 1.27 Itass 3.1.lt.2-Pcst Maintenance Testing Sales ATWS 52935 1.28 Itee 3.1.3-Fest Maintenance Testing TS Changes Sales ATWS 53016 1.29 Rescense tc SL 81-!4 MPA B-65 53445;15AP 2.23 1.!0 Ites 1.:-Fcst Trip Review Data and Inferaation Sales ATWS 53606 1.31 Ites 2.2-Ecaipstr.t Classification / Vender Inter. Sales ATWS 53689 1.32 Iteas 3.2.!!.2-Pcst Maint. Testing Precedures Sales ATWS 53772 1.33 Ites 3.2.3-Fcs: Maintenance Testing TS Changes Sales ATWS 53855 1.34 Itess 4.5.21.3-Reactor Trip Systes Testing Sales ATWS 53999 1.35 Ites 4.5.1-Reacter Systen Functional Testing Sales ATWS 54022 1.36 TS Co<ered by EL 83-36 MPA B-83 54545 1.37 TS Affected by 50.72 and .73 (GL 83-43) EPA A-18 55722 1.38 Ercand M List NUREB-0933 0660:1.F.1 1.'.9 Radiation P.ctaction Plans NURES-0933 0660:111.D.3.1 1.40 Balting Le;ra:ation or Failure NURES-0933 61-29 1.41 Floodir; of Ccecartaents by Backflcw NURE6-0933 61-77 1.42 MSL LeMage Centrol Systees NURES-0933 TAP C-08 1.43 Water Hasser NURE6-09!3 USI A-1

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1.44 Asystetric Eleacewn Lcads en Reactor Systess NURES-0933 USI A-2 1.43 Syste:s !r.ttract:ca NUREG-0933 US! A-!7

!.46 Ieters:natier. cf SR7 Fac: Dynasic Lcads NURES-0933 USl A-29 1.47 Centair.ssnt Erst;ercy Sur; Performance NURE6-0933 US! A-4:

1.43 Saist< F4:tcr cr Firstraticn I-10A 4929;

1. " Fra:te .esss: S n eil:arce Frc;ra 50 6pp. 6 & H 57464

r

, 1 Millstone 1 ISAP Issues - 3 l

• ISAP 1 Title - NU !ssues to be included in ISAP Source t

Cross Refernece Action Letters Sue PSA Nctes

+---++------ - - - + ++ - ++ --- - -+ +-, +-+ +---+

2.01 LPCI Reactely Operated Valve 1-LP-50AtB NU B 2.02 trynell Huaidity Instrumentation NU

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l 2.03 Process Cosputer Replacesent NU ISAP 1.08 2.04 High Steas Flos Setpoint increase NU A

2.03 Hydrogen Water Chemistry Study NU 2,06 Condenser Retute NU A 2.07 Sadiue Hypochicrite Systen NU C 2.38 Extraction Steas Piping NU 61-69 A 2.09 Upgrading of Piping and Instrumentation Diagrass NU ,

2.10 Drywell Ventilation Systes NU 2.!! Stud Tensiceers NU 2.12 Reactor Vessel Head Stand Relocation NU 2.13 Turtine Water Induction Modifications NU 2.14 Evaluation and laplementation of NURES-0577 NU USI A-12 Y 2.13 Torque Switch Evaluation for MOVs NU 2.16 Reactor Protection Trip Systes NU 2.17 4.16kV, 480V t 125Vdc Plant Distribution Prot. NU Ui! A-44 2.18 Spent Fuel Pool Storage Racks /Transparation Cast NU 2.19 DC Systes Review -

NU USI A-44; TAP A-30 2.20 RWCU Systes Isolation Setpoint Reduction NU 2.21 480V Load Center Repl. of Dil Filled Breaker NU Y 2.22 Control Red Drive Systes Water Hasser Analysis NU Y 2.2: Instrument, Service and Breathing Air leprve NU Y 2.24 Offsite Poner Systess NU Y 2.25 Drysell Teeperature Monitoring Systen Upgrade NU 2.26 Reliability Equipment NU 2.27 Spara Recirculation Puap Motor NU 2.28 Long Ters Cooling Study . NU US! A-45;PSS A 2.29 FNCI Assesseent Study NU USI A-45 2.30 MSIV Closure Test Frequency NU A 2.01 LPCI Lube Oil Cooler Test Frequency NU A h:tes:

1. An exemption or license asendaent say be required.

2. To date 700 of the approrisately 1074 identified sodifications have teen sade. The licensee intends to sedify 109 pipe supports before and during the 1985 refueling cutage. The resaining work is to be included in ISAP.

2. The licensee plans to casplete all of the envoronmental cualification of ele:trical ecuipsent according to the 10CFR50.49 schedule recuirerents, except for the notar operators fcr the 28 safety related MOVs. Pefore these actor operators can be installed, their effect on other ongeing projects,suchastheseisaicanalyses,needtoteevaluated.

F S '.:

A. Cuantitaive risk calculation.

I. Ergir.eering M grent.

. h:-radiological ci.blic risk.

.