ML17258B050

Forwards Revision 2 of SEP Review of Safe Shutdown Sys for Re Ginna Nuclear Power Plant, Per SEP Topic VII-3, Sys Required for Safe Shutdown. Safe Shutdown Sys Evaluation Completes Review for SEP Topics V-10.B & V-11.B

ML17258B050
Person / Time
Site:	Ginna
Issue date:	05/13/1981
From:	Crutchfield D Office of Nuclear Reactor Regulation
To:	Maier J ROCHESTER GAS & ELECTRIC CORP.
Shared Package
ML17258B052	List: ML17258B050 ML17309A158
References
TASK-05-10.B, TASK-05-11.A, TASK-05-11.B, TASK-07-03, TASK-7-3, TASK-RR LSO5-81-05-025, LSO5-81-5-25, NUDOCS 8105200263
Download: ML17258B050 (17)

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May 13,

'l981 Docket No. 50-244 LS05 05-025

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I Offuff g8 Mr. John E. Maier Vice President Electric 8 Steam Production Rochester Gas 8 Electric Corporation 89 East Avenue Rochester, New York 14649 sar R+z.

Dear Mr. Maier:

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SUBJECT:

GINNA - SEP TOPICS V-lO.B, RHR SYSTEM RELIABILITY, V 11.B, RHR INTERLOCK REQUIREMENTS, AND VII-3, SYSTEMS REQUIRED FOR SAFE SHUTDOWN (SAFE SHUTDOWN SYSTEMS REPORT)

Attached is the revised evaluation of Safe Shutdown Systems, incorporating, where appropriate, comments from your letter dated January 13, 1981.

Changes from the previous revision are marked by a double line in the margin.

The issue of--high pressure/low pressure interfaces and RHR interlock requirements (SEP Topics V-ll.Aand V-ll.B) was the subject of a recent staff safety evaluation transmitted to you by letter dated April 2I4, 1981.

The safe shutdown systemsreport has been modified to be consistent with the positions established in that letter.

Since the conclusions of our evaluation are dependent on the ultimate ability of the plant to shutdown with the specified minimum equipment,,

the staff considers that operating procedures detailing how these systems would be used for the cooldown.are neces'sary.

In regard to procedures for conducting a cooldown to cold shutdown from outside the control room, we consider it acceptable to complete this in conjunction.,with the fire protection reviev.

As discussed in Appendix A of the Safe Shutdown Systems Report, contact with raw water can lead to rapid degradation of steam generator tubes.

It is the staff's intent to minimize potential leakage through an expedi-tious cooldown and depressurization if raw water is being used for cooling.

The staff will consider any alternatives to the indicated operating pro-cedures that satisfy this intent.

8 1 o52oo PA OFHCE>

SURNAME)

OATED NRC FORM 318 RO/80) NRCM 0240 OFFICIAL RECORD COPY

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w2w "In s'ummary, the follow'i'ng staff positions wi11 be carried into the integrated

'assessment:

1.

The licensee must develop plant operating/emergency procedures for conducting a plant shutdown and cooldown using only the systems and equipment identified in Section 3.1 of the SEP Safe Shutdown Systems report.

2.

The licensee must develop plant operating/emergency procedures for conducting a plant cooldown from outside the control room.

This procedure may be developed in conjunction with the fire protection reviews, if appropriate.

3.

The licensee must install diverse interlocks on the RHR isolation valves to -'prevent opening unless RCS pressure is below RHR design pressure.

(See April 2Ã, 1981 letter.)

4.

The licensee must propose a technical specification change to require enabling the low temperature overpressure protection system whenever RHR cooling is in progress.

5.

The operating procedures for the Ginna plant should be modified to direct the operator to cooldown and depressurize to RHR initiation parameters within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> whanever the service water system is

.used for steam generator feedwater.

Depressurization methods in the procedures should include the use of PORVs, using either the plant air system or the nitrogen accumulators, if required to meet the 36-hour limit. After RHR initiation, the plant should be expeditiously placed in a cold, depressurized condition if any signs of tube leakage develop.

We now consider the safe shutdown system evaluation to be complete.

This evaluation will be a basic input to the integrated safety assessment for your facility.

This assessment may be revised in the future if your facility design is changed or if NRC criteria relating to this topic are modified before the integrated assessment is completed.

Sincerely,

Enclosure:

As stated A, $ :8L inas g/]/81 Dennis M. Crutchfield, Chief Operating Reactors Branch No.

5 Division of Licensing OFFICE/

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Docket No. 50-244 LSOS-81-'5-025 UNITED STATES NUCLEAR REGULATORY COMMISSlON WASHINGTON,D. C. 20555 May 13, 1981 Mr. John E. Maier Vice President Electric 8 Steam Production Rochester Gas 8 Electric Corporation 89 East Avenue Rochester, New York 14649

Dear Mr,

Maier:

SUBJECT; GINNA SEP TOPICS V-10,B, RHR SYSTEM RELIABILITY, V 11.B, RHR INTERLOCK REQUIREMENTS, AND VII-3, SYSTEMS REQUIRED FOR SAFE SHUTDOWN (SAFE SHUTDOWN SYSTEMS REPORT)

Attached is the revised evaluation of Safe Shutdown Systems, incorporating, where appropriate, comments from your letter dated January 13, 1981,

'hanges from the previous revision are marked by a double line in the

margin, The issue of high pressure/low pressure interfaces and RHR interlock requirements (SEP Topics V-ll,A and V-ll,B) was the subject. of a recent staff safety evaluation transmitted to you by letter dated April 2'4, 1981, The safe shutdown system report has been modified to be consistent with the positions established in that letter.

Since the conclusions of our evaluation are dependent on the ultimate ability of the plant to shutdown with the specified minimum equipment, the staff considers that operating procedures detailing how these systems would be used for the cooldown are necessary.

$n regard to procedures for conducting a cooldown to cold shutdown from outside the control

room, we consider it acceptable to complete this in conjunction with the fire protection review, As discussed in Appendix A of the Safe Shutdown Systems Report, contact with raw water can lead to rapid degradation of steam generator tubes.

It is the staff's intent to minimize potential leakage, through an expedi-tious cooldown and depressurization if raw water is being used for cooling.

The staff will consider any alternatives to the indicated operating pro-cedures that satisfy this intent,

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In summary, the following staff positions will be carried into the inteqrated assessment:

1.

The licensee must develop plant operating/emergency procedures for conducting a plant shutdown and cooldown using only the systems and equipment identified in Section 3.1 of the SEP Safe Shutdown Systems report.

2.

3.

The licensee must develop plant operating/emergency procedures for conducting a plant cooldown from outside the control room.

This procedure may be developed in conjunction with the fire protection reviews, if appropriate.

The licensee must install diverse interlocks on the RHR isolation valves to prevent opening unless RCS pressure is below RHR design

pressure, (See April 24, 1981 letter.)

4.

The licensee must propose a technical specification change to require enabling the low temperature overpressure protection system whenever RHR cooling is in progress.

5.

The operating procedures for the Ginna plant should be modified to direct the operator to cooldown and depressurize to RHR initiation parameters within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> whenever the service water system is used for steam generator feedwater.

Depressurization methods in the procedures should include the use of PORVs, using either the plant air system or the nitrogen accumulators, if required to meet the 36-hour limit, After RHR initiation, the plant should be expeditiously placed in a cold, depressur ized condition if any signs of tube leakage

develop, Me now consider the safe shutdown system evaluation to be complete.

This evaluation will be a basic input to the integrated safety assessment for your facility.,

This assessment may be revised in the future if your facility design is changed or if NRC criteria relating to this topic are modified before the integrated assessment is completed.

Sincerely, Dennis H, Crutchfield, C

ef Operating Reactors Bran No, 5

Division of Licensing Enclosure; As stated cc w/enclosure:

See next page

f,

~

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Mr. John E. Maier CC Harry H. Voigt, Esquire

LeBoeuf, Lamb, Lei by and MacRae 1333 New Hampshire Avenue, N.

W.

Suite 1100 Washington, D. C.

20036 Mr. Michael Slade 12 Trailwood Circle Rochester, New York 14618 Ezra Bial ik Assistant Attorney General Environmental Protection Bureau New York State Department of Law 2 World Trade Center New York, New York 10047 Jeffrey Cohen New York State E nergy Office Swan Street Bui lding Core 1,

Second Floor Empire State Plaza

Albany, New York 12223 Director, Technical Development Programs State of New York Energy Office Agency Building 2 Empire State Plaza

Albany, New York 12223 Rochester Public Library 115 South Avenue Rochester, New York 14604 Supervisor of the Town of Ontari o 107 Ridge Road West

Ontario, New York 14519 Resident Inspector R. E. Ginna Plant c/o U. S.

NRC 1503 Lake Road

Ontario, New York 14519 Director, Criteria and Standards Division Office of Radiation Programs (ANR-460)

U. S. Environmental Protection Agency Washington, D. C.

20460 U. S. Environmental Protection Agency Region II Office ATTN:

EIS COORDINATOR 26 Federal Plaza New York, New York 10007 Herbert Grossman, Esq.,

Chairman Atomic Safety and Licensing Board U-S. Nuclear Regulatory Comoission Washington, D. C.

20555 Dr. Richard F, Cole Atomic Sa fety and Licens i ng Board U.

S. Nuclear Regulatory Commission Washington, D. C.

20555 Dr.

Emmeth A. Luebke Atomic Safety and Licensing Board U. S. Nuclear Regulatory Cormission Washington, D. C.

20555 Mr. Thomas B. Cochran Natural Resources Defense Council, Inc.

1725 I Street, N.

W.

Suite 600 Washington, D. C.

20006 Ezra I. Bialik Assistant Attorney General Environmental Protecti on Bureau New York State Department of Law 2 World Trade Center New York, New York

10047,

I 1

REGULATORY DEFORMATION DISTRIBUTION SY EM (RIDS)

ACCESSION NBR:8105200263 DOC ~ DATE: 81/05/13 NOTARIZED:

NO DOCKET FACIL:50-204 Robert Emmet Ginna Nuclear PlantR Unit 12 Rochester G

05000244 AUTH BYNAME AUTHOR AFFILIATION CRUTCkF IELDE D ~

Operating Reactors Branch 5

REC IP R NAME.

RECIPIENT AFFILIATION MAIER~J.E'.

Rochester Gas 8 Electric Corp+

SUBJECT:

Forwards Revision 2 of "SEP Review of Safe Shutdown Sys for'E Ginna Nuclear Power Plant" per SEP T'opic VII 3E "Sys Required for Safe Shutdown."

Safe shutdown sys evaluation=

completes review for SEP Topics V-10.B 8 V-ii.B.

5M 0, + 81052.ooz6) a~7/

DISTRIBUTION CODE:

SEOIS COPIES RECEIVED:LTR ENCL /

SIZE:

TITLE:

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NOTES: 1 copy;SEP Sects Ldr ~

05000240 RECIPIENT ID CODE/NAME:

ACTION; LAINASE G ~

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~O UNITEO STATES NUCLEAR REGULATORY COMMISSION WASHINGTON,D. C. 20555 May 13, 1981 Docket No. 50-244 LS05-81-'5-025 Mr. John E. Maier Vice President Electric Ir Steam Production Rochester Gas 8 Electric Corporation 89 East Avenue Rochester, New York 14649 MAYl 9 198)Ir

-8

++++++ ac+ rce 00Jeg rgg~

Dear Mr,

Maier:

SUBJECT; GINNA ~ SEP TOPICS V-10,B, RHR SYSTEM RELIABILITY,V<<ll.B, RHR INTERLOCK REQUIREMENTS, AND VII-3, SYSTEMS REQUIRED fOR SAFE SHUTDOWN (SAFE SHUTDOWN SYSTEMS REPORT)

Attached is the revised evaluation of Safe Shutdown Systems, incorporating, where appropriate, comments from your letter dated January 13, 1981.

Changes from the previous revisioA are marked by a double line in the Illal'91 n The issue of high pressure/low pressure interfaces and RHR interlock requirements (SEP Topics V-ll,A and V-ll,B) was the subject of a recent staff safety evaluation transmitted to you by letter dated April 2'4, 1981, The safe shutdown system report has been modified to be consistent with the positions established in that letter.

Since the conclusions of our evaluation are dependent on the ultimate ability of the plant to shutdown with the specified minimum equipment, the staff considers that operating procedures detailing how these systems would be used for the cooldown are necessary.

In regard to procedures for conducting a cooldown to cold shutdown from outside the control

room, we consider it acceptable to complete this in conjunction with the fire protection review, As discussed in Appendix A of the Safe Shutdown Systems Report, contact with raw water can lead to rapid degradation of steam generator

tubes, It is the staff's intent to minimize potential leakage.through an expedi-tious cooldown end depressurization if raw water is being used for cooling.

The staff will consider any alternatives to the indicated operating pro-cedules that satisfy this intent, 8 x0.5zoo>~'&l SII WS~ ~5~- ~~(41)

K I

~'ll V~

)

-.2-In summary, the following staff positions will be carried into the integrated assessment:

1.

The licensee must develop plant operating/emergency procedures for conducting a plant shutdown and cooldown using only the systems and equipment identified in Section 3.1 of the SEP Safe Shutdown Systems report.

2.

The licensee must develop plant operating/emergency procedures for conducting a plant cooldown from outside the control room.

This procedure may be developed in conjunction with the fire protection reviews, if appropriate.

3.

The licensee must install diverse interlocks on the RHR isolation valves to prevent opening unless RCS pressure is below RHR design

pressure, (See April 24, 1981 letter.)

4.

The licensee must propose a technical specification change to require enabling the low temperature overpressure protection system whenever RHR cooling is in progress.

5.

The operating procedures for the Ginna plant should be modified to direct the operator to cooldown and depressurize to RHR initiation parameters within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> whenever the service water system is used for steam generator.feedwater.

Depressurization methods in the procedures should include the use of PORVs, using either the plant air system or the nitrogen accumulators, if required to meet the 36-hour limit, After RHR initiation, the plant should be expeditiously placed in a cold, depressurized condition if any signs of tube leakage

develop, Me now consider the safe shutdown system evaluation to be complete, This evaluation will be a basic input to the integrated safety assessment for your facility.,

This assessment may be revised in the future if your facility design is changed or if NRC criteria relating to this topic are modified before the integrated assessment is completed.

Sincerely, Enclosure; As stated Dennis H, Crutchfield, C

ef Operating Reactors Bran No, 5

Division of Licensing cc w/enclosure:

See next page

~c' l

f

Mr. John E. Maier CC Harry H. Yoigt, Esquire

LeBoeuf, Lamb, Leiby and MacRae 1333 Hew Hampshire

Avenue, N.

W.

Suite 1100 Washington, D. C.

20036 Mr. Michael Slade 12 Trailwood Circle Rochester, New York 14618 Ezra Bialik As s is tant Attorney General Environmental Protection Bureau New York State Department of Law 2 World Trade Center New York, New York 10047 Jeffrey Cohen Hew York State Energy Office Swan Street Building

~ Core 1,

Second Floor Emp i re State P 1 aza

Albany, New York 12223 Director, Technical Development Programs State of New York Energy Office Agency Building 2 Empire State Plaza

Albany, New York 12223 Rochester Public Library 115 South Avenue Rochester, New York 14604 Supervisor of the Town of Ontario 107 Ridge Road West

Ontario, New York 14519 Resident Inspector R. E. Ginna Plant c/o U. S.

NRC 1503 Lake Road

Ontario, New York 14519 Director, Criteria and Standards Division Office of Radiation Programs (ANR-460)

U. S. Environmental Protection Agency Washington, D. C.

20460 U. S. Envi ronmenta 1

P rotecti on Agency Region II Office ATTN:

E I S COORDINATOR 26 Federal Plaza Hew York, New York 10007 Herbert Grossman, Esq.,

Chairman Atomic Safety and Licensing Board U. S. Nuclear Regulatory Comnission Washington, D. C.

20555 Dr. Richard F, Cole Atomic Safety and Licensing Board U. S. Nuclear Regulatory Commission Washington, D. C.

20555 Dr.

Emmeth A. Luebke Atomic Safety and Licensing Board U. S. Nuclear Regulatory Commission Washington, D. C.

20555 Mr. Thomas B. Cochran Natural Resources Defense Council, Inc.

1725 I Street, H.

W.

Suite 600 Washington, D. C.

20006 Ezra I. Bialik Assistant Attorney General Environmental Protecti on Bureau New York State Department of Law 2 World Trade Center

,t Neh York, New York 10047

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