ML17250A362

Summary of 800605 Meeting W/Util in Bethesda,Md Re Proposed Rule Concerning Fire Protection Program for Nuclear Power Plants Operating Prior to 790101

ML17250A362
Person / Time
Site:	Ginna
Issue date:	06/26/1980
From:	Nowicki S Office of Nuclear Reactor Regulation
To:	Office of Nuclear Reactor Regulation
References
NUDOCS 8007100214
Download: ML17250A362 (17)

Text

Docket No. 50-244 JtJNE 2 6 t980 LICENSEE:

Rochester Gas and Electric Corporation (RG&E)

FACILITY:

R. E. Ginna Atomic Power Station

SUMMARY

OF FIRE PROTECTION MEETING HELD ON JUNE 5, 1980 Representatives of the Nuclear Regulatory Commission (NRC) and Rochester Gas and Electric Corporation (RG&E) met in Bethesda, Maryland NRC offices on June 5. 1980.

RG&E had requested the meeting to discuss their concerns relating to the proposed rule entitled "Fire Protection Program for Nuclear Power Plants Operating Prior to January 1, 1979" and their response to our April 25, 1980 letter transmitting 1) a list of selected issues and their status

2) Fire Protection Supplement of Staff Requirements and

3) reports of our fire protection consultants relating to the items listed in 1).

Attachment 1 is a list of attendees.

Attachment 2 provided by RG&E, includes 1) a proposed agenda for the meeting 2) RG&E's objectives for the meeting 3) a history of the Ginna Fire Protection review 4) a compilation of RG&E fire protection submittals and 5) a list of items to be discussed as responses to our April 25, 1980 letter.

Although item 3.2.1 was not on the RG&E list, it was discussed in their June 4, 1980 response to our April 25, 1980 letter and at the meeting., provided by RG&E, lists the inplementation dates for all of the modifications covered in the Pre Protection Safety Evaluation Report dated February 14, 1979 in support of License Amendment No. 24 to Provi-sional Operating License No.

DPR-18 for the R.E.

Ginna Nuclear Power Plant.

As of June 1, 1980, twenty-seven of the forty-nine modifications have been completed.

As of Novpober 1, 1980, thirty-two of the forty-nine modifica-tions are expected to be completed.

RG&E was concerned that if the new rule went into effect, seventeen items would be delinquent according to the rule.

RG&E discussed the fact that as a Systematic Evaluation Program (SEP) plant, their fire protection review had been scheduled for one of the last reviews and their fire protection SER had been issued approximately one year later than most of the licensees.

RG&E also discussed the amount of engineering and installation reqllired to complete the modifications and the apparent impossible time constraints in which to compress this work into five months.

The staff recommended that RG&E include their discussion on the schedule with",:their comments on Appendix R.

OFFICE P g-.

SURNAME OATE P.

NRC FORM 318 {9-76) NRCM 0240 AU.S. GOVERNMENT PRINTING OFFICE; 1979.289.369

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Attachment 5 provided by RG&E is a cppy of their June 4, 1980 letter transmitting their response to our April 25, 1980 Fire Protection Safety Evaluation Report Supplement without attached drawings.

The letter transmitted the previous day by RG&E formed the basis for most of the technical discussion during the meeting.. The staff commented on most of the items during the discussion and explained to RG&E that:since there was a large amount of technical detail that some of our responses would require more study and a formal, written response would follow our review.

Most of the discussion was devoted to clarification of our posi-tion and the details of the licensees'ritten response.

Several items that require additional discussion are:

3.1.11 RG&E will provide additional data and will justify the selection of 4'A H2 by volume in their response instead of 25 H2.

3.'t.21 3.1.21 3.2.1 3.2.5 3.2.7 The staff wil few weeks.

(Item 1)

RG&E will review the water density of 0.25 gpm for the wall curtain in their latest submittal compared to 0.36 gpm and will justify the new number.

(Item 2) After considerable discussion concerning the heat detectors, RG&E committed to analyze the arrange-ment to make sure the water curtain - detector system will protect the control room wll.

Ginna will analyze make-up requirements for cool down and the staff will review the evaluation at that time.

Ginna currently has procedures in place that define operator actions required for shutdown if the/'e are-fires in various fire zones within the plant."

The staff will review the response in detail before reaching conclusions on acceptability.

The June 4, 1980 letter is inaccurate in that instead of replacing pump internals as stated in the letter, the whole pumps are being replaced and tested for service.

1 prepare a written evaluation of the RG&E response within a

Enclosures:

1.

List of Attendees 2.

Agenda Or~ gfgaed bp

~'1I;Cef'~tg'tanley D. Nowicki, Project Manage Operating Reactors Branch 85 Division of Licensing OFFICE/

SURNAME OATE$..

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MEETING

SUMMARY

DISTRIBUTION:

Docket 50-244 NRC PDR Local PDR NRR Reading ORB 85 Reading H. Denton E.

Case D. Eisenhut J. Olshinski G. Lainas T. Novak R. Tedesco R. Purple S.

Varga T. Ippolito R. A. Clark R.

W. Reid D. Crutchfield S. Nowicki H. Smith TERA NSIC ACRS (16)

OIaE (3)

OELD R. Anand S.

Hudson J. Kleyan, Rolf Jensen P.

Sears J. Riesland R. Ferguson T. Lee W. Borland, RGRE R. Mecredy, RG5E E. Smith, RG5E G. Harrison, R. E. Smith, RG5E T. Wambach M. Fletcher

& Assoc, Inc.

UNITEDSTATES NUCLEAR REGULATORYCOMMISSION WASHINGTON, D. C. 20555 June 26, 1980 Docket No. 50-244 LICENSEE:

Rochester Gas and Electric Corporation '(RG&E)

FACILITY:

R.

E. Ginna Atomic Power Station

SUMMARY

OF FIRE PROTECTION MEETING HELD ON JUNE 5, 1980 Representatives of the Nuclear Regulatory COIImIission (NRC) and Rochester Gas and Electric Corporation (RG&E) met in Bethesda, Maryland NRC offices on June 5, 1980.

RG&E had requested the meeting to discuss their concerns relating to the proposed rule entitled "Fire Protection Program for Nuclear Power Plants Operating Prior to January 1,

1979" and their response to our April 25, 1980 letter transmitting

1) a list of selected issues and

~

their status

2) Fire Protection Supplement of Staff Requirements and

3) reports of out fire protection consultants relating to the items listed in 1).

Attachment 1 is a list of attendees.

Attachment 2 provided by RG&E, includes

1) a proposed agenda for the meeting 2) RG&E's objectives for the meeting 3) a history of, the Ginna Fire Protection review 4) a compilation of RG&E fire protection submittals and 5) a list of items to be discussed as responses to our April 25,,1980 letter.

Although item 3.2.1 was not on the RG&E l.ist, it was discus'sed.in their June 4, 1980 response to our April 25, 1980 letter and at the meeting.

Attaclment 3, provided by RG&E, lists the inplementation dates for all of the modifications covered in the Fire Protection Safety Evaluation Report dated February 14, 1979 in support of License Amendment No.

24 to Provi-sional Operating License No.

DPR-18 for the R.E.

Ginna Nuclear Power Plant.

As of June 1, 1980, twenty-seven of the forty-nine modifications have been completed.

As of November 1, 1980. thirty-two of the forty-nine modi.fica-tions are expected to be completed.

RG&E was concerned that if the new rule went into effect, seventeen items would be delinquent according to the rule.

RG&E discussed the fact that as a Systematic Evaluation Program (SEP) plant, their fire protection review had been scheduled for one of the last reviews and their fire protection SER had been issued approximately one year later than most of the licensees.

RG&E also discussed the amount of engineering and installation required to complete the modifications and the apparent impossible time constraints in which to compress this work-into five months.

The staff recommended that RG&E include their discussion on the schedule with their comments on Appendix R..

Attachment 5 provided by RG&E is a copy of their June 4, 1980 letter transmitting their response to our April 25, 1980 Fire Protection Safety Evaluation Report Supplement without attached drawings.

The letter transmitted the previous day by RG&E formed the basis for most of the technical discussion during the meeting.

'The staff commented on most of the items during the discussion and explained to RG&E that since there was a large amount of technical detail that some of our responses would require more study and a formal written response would follow our review.

Most of the discussion was devoted to clarification of our posi-tion and the details of the licensees'ritten response.

Several items that require additional discussion are:

3.1.11 RG&E will provide additional data and will justify the selection of 4%

H2 by volume in their response

instead, of 2X H2.

3.1.21 (Item 1)

RG&E will review the water density of 0.25 gpm for the wall curtain in their latest submittal compared to 0.36 gpm and will justify the new number.

3.1.21 (Item 2) After considerable discussion concerning the heat detectors, RG&E committed to analyze the arrange-ment to make sure the water curtain - detector

system, will protect the control room wall.

3.2.1 Ginna will analyze make-up requirements for cool down and the staff will review the evaluation at'that time.

Ginna currently has procedures in place that define operator actions required for shutdown if there are fires in various fire zones within the plant.

3.2.5 The staff will review the response in detail before reaching conclusions on acceptability.

3.2.7 The June 4, 1980 letter is inaccurate in that instead of replacing pump internals as stated in the letter, the whole pumps are being replaced and -tested for service.

The staff will prepare a written evaluation of the RG&E response within a few weeks.

e Stanley cki, Project Manager Operating Reactors Branch 85 Division of Licensing

Enclosures:

1.

List of Attendees 2.

Agenda 3.

Table 3.1 - Implementation Date for Modification 4.

RG&E letter dated June 4, 1980

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cc w/enclosures:

Harry H. Voigt, Esquire

LeBoeuf, Lamb, Leiby 5 MacRae 1757 N Street, N.

W.

Washington, D.

C.

20036 Mr. Michael Slade 12 Trailwood Circle Rochester, New York 14618 Rochester Coomittee for Scientific Information Robert E. Lee, Ph.D.

P. 0.

Box 5236 River Campus Station Rochester, New York 14627 Jeffrey Cohen New York State Energy Office Swan Street Building Core 1, Second Floor Empire State Plaza Alba',

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 Director, Technical Assessment Division Office of Radiation Programs (AW-459)

U. S. Environmental Protection Agency Crystal Mall g2 Arlington, Virginia 20460 U. S. Environmental Protection Agency Region II Office ATTN:

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

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

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

20555 Dr.

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

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

1725 I Street, N.

W.

Suite 600 Washington, D. C.

20006 Mr. Leon D. White, Jr.

Vice President Electric and Steam Production Rochester.Gas 8 Electric Corporation 89 East Avenue Rochester, New York 14649

Enclosure 1

ATTENOEES - FIRE PROTECTION - JUNE 5

1980 Stan Nowicki Raj Anand Scott Hudson Jack Kievan Pat Sears John Riesland Robert Ferguson T. Lee William Borland Robert Mecredy Edward Smith Greg Harrison Robert E. Smith Tom Wambach Mike Fletcher PM - ORB 85 NRR/OL NRC/NRR - Chemical Engineering NRC/NRR - Chemical Engineering Rolf Jensen 8 Assoc, Inc.

NRC - Chemical Engineering I

8 E - DROI NRC -

DE NRC/RES.

RG&E Project Manager

RGSE, Manager, Nuclear Engineering RGSE, Fir e Protection Engineer NRC, Fire Protection RGB - Assistant Chief Engineering NRC/NRR NRC/NRR

Attachment 2

Agenda RG&H/WRC Meetinc}

Ginna Fire Protection June 5,

1980 1.

~Ob ective of Meeting 2.

History of Ginna Fire Protection Review a.

SER items completed as of June I, 1980 b.

SER items expected to be completed by November 1,

1980 4.'Res onses to WRC's letter of April 25, l980 5.

Discussion of Proaosed Ap endix R to 10 CFR 50 a.

Clari fications and questions on Technical Requirements b.

Comments on Schedule

~Ob'ective of Meeting To attempt to resolve open SER items by. discussing'ur response to the NRC's.letter of April 25, 19g.

To discuss the technical issues raised in Appendix

.R including clarification of requirements as necessary.

To discuss our schedule for completing fire modifications.

History of Ginna Fire Protection Review o

Browns Ferry Fire

March 22,-1975 o

NRC Letter Requesting Fire Study

May ll, 1976 September 28, 1976 o

Ginna Submittal

February 24, 1977 o

NRC Site Visit

June 27-30, 1978 o

NRC Safety Evaluation Report

February 14, 1979 o

NRC Letter Providing Proposed Appendix R

Nay 19, 1980

RG&E Submittals I

2/14/77 5/15/78 6/9/78 6/26/78 6/27/78 9/1/78 9/22/78 10/18/78 10/31/78 3/13/79 3/19/79 4/30/79 5/?5/79 6/14/79 6/29/79 7/27/79 9/28/79 11/14/79 12/18/79 12/21/79 12/28/79 2/12/80 5/23/80 5/29/80 Initial Submittal

Response

to 2/14/78 NRC letter

Response

to 5/3/78 NRC letter

Response

to 6/8/78 NRC letter

Response

to 5/3/78 NRC letter

Response

to 7/20/78 NRC letter

Response

to 7/20/78 NRC letter Information on "superwall"/doors

Response

to 10/6/78 NRC letter Comments on 2/14/79 SER Schedule for RGE submittals Information 3.1.24, 3.1.25, 3.1.43, 3.2.4 Fire Brigade (3.2.9), Information on 3.1.11 Completion of 3.1.6 delayed to 8/31/79 Infotmation on 3.2.7 Completion of 3.1.4 delayed to 10/1/79 Information on 3.1.2, 3.'1.21, 3.1.46, 3.1.48, 3.2.6 Tech.

Spec.

submittal on fire brigade (3.2.9)

Information on 3.1.39 Completion delays on 3.1.5 (6/1/80), 3.1.24 (6/1/80),

3. 1. 34 (3/31/80),

3. 2. 8 (6/1/80)

Information on 3.2.5 Information on 3.7.1, 3.2.2 Information on 3. 2. 5 (clarification of propri'etary status)

Completion delays on 3.1. 8 (6/81),

3.1.11 (12/80),

3.1.21 (6/81), 3.1.48 (12/80), 3.1.49 (9/80)

Information 3.1.5, 3.1.8, 3.1.34.

3.2.8

Responses to April 25, 1980 f.etter o

Items to be Discussed 3.1.2 3.1.11 3.1.21 3.1.24 3.1.25 3.1.39 3.1.~3 3.1.48 3.2.2 3.2.5 3.2.6

3. 2.7 Suppression System Battery Room Ventilation Control Room Separation Piping and Duct Penetrations-Construction Joints RCP Oil Collection System Detector Testing Hydrogen Piping Cable Separation Cable Penetrations Backflow Protection Fire Pump Performance TARLE 3.1 I)IMPLEMENTATION DATE FOR )IODIFICWTIOM ITEMS

'3. 1. 1 3.1.2 3.1.3 3.1.~

3.1.5 3.1.6 3.1.7 3.1.8 3.1.9 3.1.10 3.1. 11

3. l. 12 3.1.13 3.1.14 3..1.15 3.1;16 3.1. 17 3.1.18 3.1.19

3. l. 20

3. 1. 21 3.1.22 3.1.23 3.1.24 3.1.25

.3.1.2)

3. l. 27

3. 1. 28 3.1.29

3. l. 30

'3. l. 31

3. l. 32

3. l. 33

3. 1. 34 3.1. 35

3. 1. 3~

. 3.1. 37 Pire Detection Systems hater Sunression Systems and Equipment Gas Supression Systems and Equipnent Curbs Fi re Doo rs Computer Room Ceil inq'~'ater Soray Shields Fire Barr'iers Pi re Dampers Halon Storage Battery Room V ntilation Fire Alarms Relocation of Gas Meter Diesel Generator Room Manhole Covers Flame Retardant Cable Coating Door Closure Adjustment Turbine Oil Reservoir Area Physical Examination Diesel Room LIater Supression System Service

's'ater Piping in Diesel Room Controi Room Separation Exterior Hydrants Emergency Lights Piping and Duct <<Penetrations Construction

,'Joints Exterior Hose Houses Special Purpose Fire Fighting Equipment Fire Fighting Equioment Storage Diesol Fire Pump Testing

& Surveillance Fire Door Supervision Brigade Training Control of Combustibles Control of Ignition Sources Prefire Strategi'es Of f-Duty Briqade Recall Hose Stretch Tests Fire Dancers STATUS 6/1/80 12/80 5/81 cj/8 1 Complete

~/80 Complete 4/A]

6/80

$/Al Complete r)/80 12/80 Complete Complete Complete Complete Complete Complete 5/A 1 Compiete 6/AO Conpl etc Conplete r)/8 0 6/80 Complete Complete Complete Complete 0)/80 Complete Compol e te Complete Comol etc Complete Comolete

~/Al ESTIMATED STATUS II/I/80 12/80 6/81 r)/81 Complete Complete Complete f)/8 1 r/nl R/Al Complete 12/80 12/AO Complete Complete Complete Compol e to Complete Complete r /81 Complete 6/Ol Complete Complete Complete Complete Conplete Conpl etc Complete Complete Complete Complete Complete Complete Complete

, Complete Complete 6/Rl II

'3-11

4, ITE!!S TABLE '3.1 (Continued) 1:ST IRATED STATUS STATUS 6/1/'RO

~

ll/1/90 3.1.3~

3. 1. 39 3.1. 40 3.1. ~l 3.1. 42

3. 1. 43

3. l. 44 3.1. 45

3. 1.

4'.l. 47

3. 1. 49 3.1.49 12/80 t~/P 1 12/oO 12/80 Complete:

Complete Complete Complete 6/RO 6/PO Fire Barriers Complete Reactor Coolant Pump Lube Oil Collection fi/~l System Fire '.~ater Piping System Manual Hose Stations Inside Containment Signaling Circuits Supervision Detector Testing Evterior Hydrant Freeze Protection 4iorking Permit Involving Ignition Source Auxiliary Boiler Transient

'ombustibles Hydrogen Piping t<itchen Area Complete 6/Rl 17./RO

~/81 1 2/'3 0 12/P 0 Complete Complete Complete Complete

, 12/BQ Complete