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g      g{                                                         100 Interpace Parkway Parsippany, New Jersey 07054 2G1263-6500 TELEX 136-482                 i Wnter's Direct Dial Number June 30, 1982 Mr. Dennis M. Crutchfield, Chief Operating Reactors branch iD Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C. 20535
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100 Interpace Parkway Parsippany, New Jersey 07054 2G1263-6500 TELEX 136-482 i
Wnter's Direct Dial Number June 30, 1982 Mr. Dennis M. Crutchfield, Chief Operating Reactors branch iD Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C.
20535


==Dear Mr. Crutchfield:==
==Dear Mr. Crutchfield:==
==Subject:==
==Subject:==
Oyster Creek Nuclear Generating Station Docket No. 50-219 Fire Protection, 10 CFR 50.48 The enclosed information is provided in response to your letter of April 30, 1982, addressed to Mr. P. B. Fiedler.
Oyster Creek Nuclear Generating Station Docket No. 50-219 Fire Protection, 10 CFR 50.48 The enclosed information is provided in response to your letter of April 30, 1982, addressed to Mr. P.
Enclosure No. 1 of this submittal is entitled, "0yster Creek Nuclear Generating Station Appendix R Fire Evaluation Report." The report documents the results of the reassessmen; of the fire protection features at the Oyster
B. Fiedler.
;      Creek Plant for conformance to the specific requirements of Section III.G of Appendix R to 10 CFR 50 and identifies modifications to meet the requirements or alternatively, exemptions from the requirements based upon the fire hazards analysis. Section 2.0 of Enclosure (1) provides an executive summary h igh i t gh t ing th e significant findings and makes recommendations for resolving identified problems, addresses the items in the rewrite of Section 8 of Enclosure I to generic letter 81-12, and discusses the disposition of the various associated circuits defined in th e rewrite of generic letter 81-12.
Enclosure No.
Section 2.0 also identifies the areas for which we are requesting exemption from some of the requirements of Appendix R III.G.               Section 5.0 of Enclosure (1) provides additional justification for th e hardware related exemptions identified in Section 2.0. Appendix D of the enclosure provides the conceptual design information of tne alternate shutdown system.               For additional clarity, the areas for which we are seeking exemptions have been reproduced in Enclosure No. 5 to this letter.
1 of this submittal is entitled, "0yster Creek Nuclear Generating Station Appendix R Fire Evaluation Report."
The report documents the results of the reassessmen; of the fire protection features at the Oyster Creek Plant for conformance to the specific requirements of Section III.G of Appendix R to 10 CFR 50 and identifies modifications to meet the requirements alternatively, exemptions from the requirements based upon the fire hazards or analysis.
Section 2.0 of Enclosure (1) provides an executive summary h igh i t gh t ing th e significant findings and makes recommendations for resolving identified problems, addresses the items in the rewrite of Section 8 of Enclosure I to generic letter 81-12, and discusses the disposition of the various associated circuits defined in th e rewrite of generic letter 81-12.
Section 2.0 also identifies the areas for which we are requesting exemption from some of the requirements of Appendix R III.G.
Section 5.0 of Enclosure (1) provides additional justification for th e hardware related exemptions identified in Section 2.0.
Appendix D of the enclosure provides the conceptual design information of tne alternate shutdown system.
For additional clarity, the areas for which we are seeking exemptions have been reproduced in Enclosure No. 5 to this letter.
DOb 3
DOb 3
8207080209 820630                                                                                i /
i /
PDR ADOCK 05000219 F                  PDR
8207080209 820630 PDR ADOCK 05000219
                                                                                                .)b &
.)b &
GPU Nuclear is a part of the General Pubhc Utihties System
F PDR GPU Nuclear is a part of the General Pubhc Utihties System


o s
o s
Mr. Dennis M. Crutch field                   Page 2                       June 30, 1982 l
Mr. Dennis M. Crutch field Page 2 June 30, 1982 l
Enclosure No. 2 to th is letter provides the updated Fire Hazards Analysis Report and Fire Protection Program, while Enclosure No. 3 provides procedure guidelines to accomplish shutdown using the alternate shutdown systems.
Enclosure No. 2 to th is letter provides the updated Fire Hazards Analysis Report and Fire Protection Program, while Enclosure No. 3 provides procedure guidelines to accomplish shutdown using the alternate shutdown systems.
Enclosure No. 4 to this letter provides the plans and schedules necessary to implement the altern. ate shutdown system consistent with site associated constraints.       The schedule assumes NRC approval of the alternate shutdowr.
Enclosure No. 4 to this letter provides the plans and schedules necessary to implement the altern. ate shutdown system consistent with site associated constraints.
system being received by December 1982, the availability of qualified vendors
The schedule assumes NRC approval of the alternate shutdowr.
-    and material, the existing workload, the complexity of th e work, and the fact l   that a shutdown is required to verify existing design.       In light of the above, GPU Nuclear will not be able to complete the modifications by cycle 10/11 refueling outage (scheduled to start in 1984) as stipulated in 10 CFR 50.48.
system being received by December 1982, the availability of qualified vendors and material, the existing workload, the complexity of th e work, and the fact l
Therefore, we are requesting that the date required for completion of the alternate s hu tdc,wn systems be extended to cycle 11/12 refueling outage (tentatively scheduled to start in 1987) .
that a shutdown is required to verify existing design.
With respect to other Appendix R III.G modifications, because of our present workload and the fact that sc .e of the modifications will require the plant to be shutdown in order to be installed, we are requesting the following schedule exemption be granted:       all modifications that do not require a plant shutdown will be completed by December 31, 1984, all modifications requiring the planc to be shutdown wtll be completed before th e startup from our cycle 10/11 outage presently scheduled to begin in late 1984.
In light of the above, GPU Nuclear will not be able to complete the modifications by cycle 10/11 refueling outage (scheduled to start in 1984) as stipulated in 10 CFR 50.48.
Therefore, we are requesting that the date required for completion of the alternate s hu tdc,wn systems be extended to cycle 11/12 refueling outage (tentatively scheduled to start in 1987).
With respect to other Appendix R III.G modifications, because of our present workload and the fact that sc.e of the modifications will require the plant to be shutdown in order to be installed, we are requesting the following schedule exemption be granted:
all modifications that do not require a plant shutdown will be completed by December 31, 1984, all modifications requiring the planc to be shutdown wtll be completed before th e startup from our cycle 10/11 outage presently scheduled to begin in late 1984.
Delaying th e implementation of the subject Appendix R requirements will not result in undue risk to the health and safety of the public because of the existing upgraded fire protection system at the plant and because the available shift manning ensures sufficient personnel are available to shutdown the plant with the existing facilities.
Delaying th e implementation of the subject Appendix R requirements will not result in undue risk to the health and safety of the public because of the existing upgraded fire protection system at the plant and because the available shift manning ensures sufficient personnel are available to shutdown the plant with the existing facilities.
Enclosure No. 5 of th is letter provides a list of exemptions from the hardware requirements of 10 CFR 50.48.
Enclosure No.
fue information contained in this submittal is correct to the best of our knowledge. Additional information to that contained in this submittal will be provided, if required, to support your review and approval of the subject modification.       If, during the development of th e detail design, we determine th a t additions, changes, updates or corrections are needed, we will notify you of such.
5 of th is letter provides a list of exemptions from the hardware requirements of 10 CFR 50.48.
                                        ~.     -
fue information contained in this submittal is correct to the best of our knowledge.
Additional information to that contained in this submittal will be provided, if required, to support your review and approval of the subject modification.
If, during the development of th e detail design, we determine th a t additions, changes, updates or corrections are needed, we will notify you of such.
~.


Mr. Dennis M. Crutchfield           -            Page 3             June 30, 1982 If additional information or clarification is required, please contact Mr.
Mr. Dennis M. Crutchfield Page 3 June 30, 1982 If additional information or clarification is required, please contact Mr.
J. Knubel a t (201) 299-2264.
J. Knubel a t (201) 299-2264.
Very truly yours, f)
Very truly yours, f) l Peter'B. Fiedler Vice President and Director Oyster Creek PBF:JK:rss Enc losu re s :
Peter'B. Fiedler l
1.
Vice President and Director Oyster Creek PBF:JK:rss Enc losu re s :   1. Fire liazards Analysis, Appendix R Fire Evaluation Report
Fire liazards Analysis, Appendix R Fire Evaluation Report 2.
: 2. Fire liazards Analysis Report
Fire liazards Analysis Report 3.
: 3. Alternate Shutdown Capability Procedure Guidelines
Alternate Shutdown Capability Procedure Guidelines 4.
: 4. 10 CFR 50 Appendix R Modifications Schedule
10 CFR 50 Appendix R Modifications Schedule 5.
: 5. Exemptions from the liardware Requirements of 10 CFR 50.48 cc:   Mr. Ro nald C. Ila yne s , Ad minis tra tor Region I U.S. Nuclear Regulatory Commission 6 31 Park Avenue King o f Prussia, PA       19406 NRC Resident Inspector Oyster Creek Nuclear Generating Station Forked River, NJ       08731
Exemptions from the liardware Requirements of 10 CFR 50.48 cc:
 
Mr. Ro nald C. Ila yne s, Ad minis tra tor Region I U.S. Nuclear Regulatory Commission 6 31 Park Avenue King o f Prussia, PA 19406 NRC Resident Inspector Oyster Creek Nuclear Generating Station Forked River, NJ 08731
  *e ENCLOSURE t/3 OYSTER CREEK ALTERNATE SHUTDOWN CAPABILITY PROCEDURE GUIDELINES Proceduro Guidelines - Safe Shutdown From Outside the Control Room Plant procedures will be developed which will direct the operators in the tasks to be performed to achievo and maintain hot shutdown from outside the control room with or without offsite power, and to subsequently come to cold shutdown. The existing plant procedure titled " Fire in the Control Room" is not sufficient for this purpose and will be replaced.
* e ENCLOSURE t/3 OYSTER CREEK ALTERNATE SHUTDOWN CAPABILITY PROCEDURE GUIDELINES Proceduro Guidelines - Safe Shutdown From Outside the Control Room Plant procedures will be developed which will direct the operators in the tasks to be performed to achievo and maintain hot shutdown from outside the control room with or without offsite power, and to subsequently come to cold shutdown. The existing plant procedure titled " Fire in the Control Room" is not sufficient for this purpose and will be replaced.
The following is an outline of the shutdown procedures:
The following is an outline of the shutdown procedures:
1.0 When a decision is made to evacuate the control room due to a fire in       ,
1.0 When a decision is made to evacuate the control room due to a fire in the control room or cable spreading room, operators will attempt to complete the following actions prior to evacuating the control room:
the control room or cable spreading room, operators will attempt to complete the following actions prior to evacuating the control room:
1.1 Scram the reactor and close MS1V's.
1.1   Scram the reactor and close MS1V's.
1.2 Trip feedwater pumps.
1.2 Trip feedwater pumps.
1.3 Trip recirculation pumps.
1.3 Trip recirculation pumps.
1.4 Put isolation condenser B into service.
1.4 Put isolation condenser B into service.
1.5 Verify all rods are in and the reactor is subcritical.
1.5 Verify all rods are in and the reactor is subcritical.
1.6 Trip the turbine.
1.6 Trip the turbine.
2.0 Operators will remove all portable radios from the control room and shift supervisors office and proceed to assigned locations at the remote shut-down panel and transfer switches.
2.0 Operators will remove all portable radios from the control room and shift supervisors office and proceed to assigned locations at the remote shut-down panel and transfer switches.
3.0 Remote shutdown panel controls will be activated by operation of the transfer switches and the action will be confirmed at the remote shutdown panel.
3.0 Remote shutdown panel controls will be activated by operation of the transfer switches and the action will be confirmed at the remote shutdown panel.
4.0 Steps 1.1 through 1.4 above will be confirmed or will be performed at the remote shutdown panel if not completed prior to evacuating the control room. Reactor suberiticality will be confirmed using remote shutdown panel neutron monitoring instrumentation.
4.0 Steps 1.1 through 1.4 above will be confirmed or will be performed at the remote shutdown panel if not completed prior to evacuating the control room.
Reactor suberiticality will be confirmed using remote shutdown panel neutron monitoring instrumentation.
5.0 Operate isolation condenser B to maintain reactor pressure below 1000 psig.
5.0 Operate isolation condenser B to maintain reactor pressure below 1000 psig.
Do not exceed a 100*F/hr cooldown rate.
Do not exceed a 100*F/hr cooldown rate.
6.0 Locally confirm proper operation of the diesel generators if required by loss of offsite power.
6.0 Locally confirm proper operation of the diesel generators if required by loss of offsite power.
7.0 Avoid reactor vessel inventory loss through low pressure systems by closing and maintaining closed the following valves:
7.0 Avoid reactor vessel inventory loss through low pressure systems by closing and maintaining closed the following valves:
7.1 Cleanup system isolation valves.
7.1 Cleanup system isolation valves.
7.2 Core spray parallel valves or test valves.
7.2 Core spray parallel valves or test valves.


        ~
~
h ENCI.0SURE #3 (Contd) 8.0 Operate the CRD hydraulic system to maintain reactor water level above the low level scrau setpoint and below the bottom of the ise,lation condenser steam line.
h ENCI.0SURE #3 (Contd) 8.0 Operate the CRD hydraulic system to maintain reactor water level above the low level scrau setpoint and below the bottom of the ise,lation condenser steam line.
9.0 Makeup to the isolation condenser shell as required to keep the water level above the top of the isolation condenser tube bundles by locally starting a condensate transfer pump and operating the isolation condenser makeup valves from the remote shutdown panel or locally. If condensate water is exhausted, locally valve in fire protection water to the IC shells.
9.0 Makeup to the isolation condenser shell as required to keep the water level above the top of the isolation condenser tube bundles by locally starting a condensate transfer pump and operating the isolation condenser makeup valves from the remote shutdown panel or locally. If condensate water is exhausted, locally valve in fire protection water to the IC shells.
Line 92: Line 106:
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1 r                                                 OYSTER CREEK 10 CFR 50 AF NOTE 1                                                                                   ,
r OYSTER CREEK 10 CFR 50 AF NOTE 1 i
i                                                      1982                                                 1983 3rd OTR         4th OTR         ISt OTR       g 2nd OTR           3rd OTR         g 4th OTR       1s0 l                 , SCHEDULED CYCLE 9/IO OJTAGE SuewrTAL                    f NOTE 3           i  gggt, t
1982 1983 3rd OTR 4th OTR ISt OTR 2nd OTR 3rd OTR 4th OTR 1s0 g
norE iO Not M UPDATE FIRE HAZARD
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  /ALTERN ATE SHUTDOWN-v CAP.AB!LITa-                                                             NRC APPROVAL /
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NRC APPROV AL REQUIRED /                                                            START Fif4AL                                                       ISSUE SHUTDOWt1 REQUIRED                                                              Ef4GINEERING                               ISSUE BIO             LAST P.O.
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                                                                                        "''''                              *      "' "'*''              o         ''
/ LTERN ATE SHUTDOWN-A v
REMOTE SHUTDOWN PANEL O COMPLETE f4RC APPROVAL /
CAP.AB!LITa-COuPtyTc NRC APPROV AL REQUIRED /
START PRELIM           START FINAL ISCUE DID                           I SUE ENGR             Ef4GINEERING         REQUEST             's LA ST P'O' v                           9         "
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MODIFICATIONS TO LOCAL PANEL,S O",                  t                 .                l,
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EN     E     G' PROT 56TidN E6UIPTM'E!RT                                                 !                    ,                      s RECUEST ISSUE
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NRC APPROVAL REQUIRED /
V '' ' ' '                  "
O SHUTDOWN REQUIRED i
SHUTDOWN REQUIRED                           O                                                                                        i h                                               f4RC APPROVAL' / f f                                                 START FINAL EldCli.EERINC/           ISSUE ISSUE BID           L AST P.O.
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NRC APPROVAL REOUIRED/                                             -                                !                g REQUEST                  U SHUTDOWNNOT REQUIRED                           O                                                                         f40TE 4 START FINAL           ISSUE DID                 ISSUE EI;GifiEERif4G         REQUEST                 L A ST P.O.
EldCli.EERINC/
NRC APPROVAL NOT REQUIRED /                                                                                                g f20TE 4                 g V
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Q GMUTDOWN REQUIRED                                                                _
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START FINAL                                         ISSUE EllGli l, EERING           RLOUES1 N30 APPROVAL NOT REQUIRED / ,                                                                                           gnOTE 4         l LAST    g P.O.
NRC APPROVAL REOUIRED/
SH'JTDOWN NOT REQUIRED                       Q                                                   }
SHUTDOWNNOT REQUIRED O
: 1. THis PorCOC CD PL AN FCA MDCIFICATIONS IMPLEMENTING ICCFR50, APPENDtX R, IS DEPENDA!1T C'. ' 'C ACCEPTA*. E CF THE UPDATED CYSTER CREEK FIRE HAZ ARDS Af;ALYC:3 'Tre ;T ONCLUNG THE AF PENDix R EV ALUAT:C'3. THE PROPOSED PLAN ASSU?.'ES f.RC AffiiUVAL Or THE I CCFR50 APFEf 4DtX R PROGRAM WITHOUT CHANCE IN SCOPE.                       ,
f40TE 4 START FINAL ISSUE DID ISSUE NRC APPROVAL NOT REQUIRED /
EI;GifiEERif4G REQUEST L A ST P.O.
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: 1. THis PorCOC CD PL AN FCA MDCIFICATIONS IMPLEMENTING ICCFR50, APPENDtX R, IS DEPENDA!1T C'. ' 'C ACCEPTA*. E CF THE UPDATED CYSTER CREEK FIRE HAZ ARDS Af;ALYC:3 'Tre ;T ONCLUNG THE AF PENDix R EV ALUAT:C'3. THE PROPOSED PLAN ASSU?.'ES f.RC AffiiUVAL Or THE I CCFR50 APFEf 4DtX R PROGRAM WITHOUT CHANCE IN SCOPE.
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: 2. CYCLE 9/ t C OJT AGE IS SCHEDULED TO START JANUARY I 5,1983. Aff9 IS EXPECTED EtiGINEERING TO Ef 0 BY DECE ''EER 31. I SS3. CYCLE 10/ I I OUTACE IS SChENLED TO START IN TC 4th CU ARTER CF 1984 AND IS EXPECTED TO LAST 9 frNTHS. CYCLE I 1/12 OTHER f.elLESTONES             OUT AM 13 FFCTED TO ST ART If4 THE I st OUARTER OF 1987 DURATION IS f40T 9       AS INDICATED               DCTER:.'J i D i ET                                                                                       ,
: 2. CYCLE 9/ t C OJT AGE IS SCHEDULED TO START JANUARY I 5,1983. Aff9 IS EXPECTED EtiGINEERING TO Ef 0 BY DECE ''EER 31. I SS3. CYCLE 10/ I I OUTACE IS SChENLED TO START IN TC 4th CU ARTER CF 1984 AND IS EXPECTED TO LAST 9 frNTHS. CYCLE I 1/12 OTHER f.elLESTONES OUT AM 13 FFCTED TO ST ART If4 THE I st OUARTER OF 1987 DURATION IS f40T 9
: 3. NPC APPPOVAL YUST BE RECElVED DY THIS DATE TO ALLOW IMPLEMENTATION                                       F COMPLETION                       IN ACCOROANCE WITH THE SCHECULE FRCCOLED.
AS INDICATED DCTER:.'J i D i ET
                                    ^    '
: 3. NPC APPPOVAL YUST BE RECElVED DY THIS DATE TO ALLOW IMPLEMENTATION F
: 4. :mcw TO f 550!f 4G P.O. TO SEl.ECTED VENDOR. GFUN f?JST COMPILE DID REQUEST f
COMPLETION IN ACCOROANCE WITH THE SCHECULE FRCCOLED.
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PEN JIX R MlODIF; CATIONS SCHEDULE                                                                                                                                                                                 """
PEN JIX R MlODIF; CATIONS SCHEDULE
                                                                                                                                                                                                                                  """f 1984                                                                                                                             1985                                                     1987
"""f 1984 1985 1987
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N Enclosure 5 Exemptions f rum the Hardware Requirements of 10 CFR 50.48 Exemptions are required for the below listed areas from the requirement of providing additional automatic fire suppression / detection when 1-hour barriers are utilized. The specific justifications for these exemptions are provided in Section 5.0 of the "0yster Creek Nuclear Cenerating Station Appendix R Fire Evaluation Report." !!owever , in general the justifications for the exemptions are based on the low combustible loading in each of the areas and the other fire protection features that are already inplace within each area.
N Exemptions f rum the Hardware Requirements of 10 CFR 50.48 Exemptions are required for the below listed areas from the requirement of providing additional automatic fire suppression / detection when 1-hour barriers are utilized.
Fire Area / Zone                                                 Anticipated De si;m a t i oa                     Description               !!od i fi ca t ion s FZ-1B               Reactor Building, elevation 95'             I or   2 FZ--1 C             Reacter Luildind, elevation 75'             1 or   2 FZ-lD               Reactor Euilding, elevation 51'             I or   2 FZ-lE               Reactor   Building, elevation 23'             1 or   2 FZ-lF               Reactor Euilding, elevation 19'             1 or   2 FA-3A               IC 4160V Emergency Switchgear                 1 or   2 Vaults FA-6                 Switchgear Room                               1 or 2 FZ-SA               t!G Set Room                                   1 or 2 FZ-8C               A&B Battery Room, Tunnel and                   I or 2 Tray Roon F7. -10A             Service Building, elevation 46'               I or 2 FZ-100               Service Euilding                               1 or 2 FZ-1IB               Turbine Lube Oil Storage, Punping             1 or 2 and Purification Area FZ-llc               Switchgear Room, west end of                   1 or 2 Turbine Euilding on !!czzanine 1, eve l FZ-llD               Basement Floor South end                     1 or 2 FZ-llE               Condenser Bay                                 1 or 2 FA-14               Circulating Water Intake                     2 FA-19               Old Radwaste Building                         1 or 2 1-Cable rerouting 2-P rov id e 1-hour protective barriers                                             *}}
The specific justifications for these exemptions are provided in Section 5.0 of the "0yster Creek Nuclear Cenerating Station Appendix R Fire Evaluation Report."
!!owever, in general the justifications for the exemptions are based on the low combustible loading in each of the areas and the other fire protection features that are already inplace within each area.
Fire Area / Zone Anticipated De si;m a t i oa Description
!!od i fi ca t ion s FZ-1B Reactor Building, elevation 95' I or 2 FZ--1 C Reacter Luildind, elevation 75' 1 or 2 FZ-lD Reactor Euilding, elevation 51' I or 2 FZ-lE Reactor Building, elevation 23' 1 or 2 FZ-lF Reactor Euilding, elevation 19' 1 or 2 FA-3A IC 4160V Emergency Switchgear 1 or 2 Vaults FA-6 Switchgear Room 1 or 2 FZ-SA t!G Set Room 1 or 2 FZ-8C A&B Battery Room, Tunnel and I or 2 Tray Roon F7. -10A Service Building, elevation 46' I or 2 FZ-100 Service Euilding 1 or 2 FZ-1IB Turbine Lube Oil Storage, Punping 1 or 2 and Purification Area FZ-llc Switchgear Room, west end of 1 or 2 Turbine Euilding on !!czzanine 1, eve l FZ-llD Basement Floor South end 1 or 2 FZ-llE Condenser Bay 1 or 2 FA-14 Circulating Water Intake 2
FA-19 Old Radwaste Building 1 or 2 1-Cable rerouting 2-P rov id e 1-hour protective barriers
*}}

Latest revision as of 16:46, 17 December 2024

Forwards Fire Hazards Analysis App R Fire Evaluation Rept, Fire Hazards Analysis Rept, Alternate Shutdown Capability Procedure guidelines,10CFR50 App R Mod Schedule & Related Info,In Response to 820430 Request
ML20054L524
Person / Time
Site: Oyster Creek
Issue date: 06/30/1982
From: Fiedler P
GENERAL PUBLIC UTILITIES CORP.
To: Crutchfield D
Office of Nuclear Reactor Regulation
Shared Package
ML20054L525 List:
References
NUDOCS 8207080209
Download: ML20054L524 (7)
v • d • e


Text

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e GPU Nuclear

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100 Interpace Parkway Parsippany, New Jersey 07054 2G1263-6500 TELEX 136-482 i

Wnter's Direct Dial Number June 30, 1982 Mr. Dennis M. Crutchfield, Chief Operating Reactors branch iD Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C.

20535

Dear Mr. Crutchfield:

Subject:

Oyster Creek Nuclear Generating Station Docket No. 50-219 Fire Protection, 10 CFR 50.48 The enclosed information is provided in response to your letter of April 30, 1982, addressed to Mr. P.

B. Fiedler.

Enclosure No.

1 of this submittal is entitled, "0yster Creek Nuclear Generating Station Appendix R Fire Evaluation Report."

The report documents the results of the reassessmen; of the fire protection features at the Oyster Creek Plant for conformance to the specific requirements of Section III.G of Appendix R to 10 CFR 50 and identifies modifications to meet the requirements alternatively, exemptions from the requirements based upon the fire hazards or analysis.

Section 2.0 of Enclosure (1) provides an executive summary h igh i t gh t ing th e significant findings and makes recommendations for resolving identified problems, addresses the items in the rewrite of Section 8 of Enclosure I to generic letter 81-12, and discusses the disposition of the various associated circuits defined in th e rewrite of generic letter 81-12.

Section 2.0 also identifies the areas for which we are requesting exemption from some of the requirements of Appendix R III.G.

Section 5.0 of Enclosure (1) provides additional justification for th e hardware related exemptions identified in Section 2.0.

Appendix D of the enclosure provides the conceptual design information of tne alternate shutdown system.

For additional clarity, the areas for which we are seeking exemptions have been reproduced in Enclosure No. 5 to this letter.

DOb 3

i /

8207080209 820630 PDR ADOCK 05000219

.)b &

F PDR GPU Nuclear is a part of the General Pubhc Utihties System

o s

Mr. Dennis M. Crutch field Page 2 June 30, 1982 l

Enclosure No. 2 to th is letter provides the updated Fire Hazards Analysis Report and Fire Protection Program, while Enclosure No. 3 provides procedure guidelines to accomplish shutdown using the alternate shutdown systems.

Enclosure No. 4 to this letter provides the plans and schedules necessary to implement the altern. ate shutdown system consistent with site associated constraints.

The schedule assumes NRC approval of the alternate shutdowr.

system being received by December 1982, the availability of qualified vendors and material, the existing workload, the complexity of th e work, and the fact l

that a shutdown is required to verify existing design.

In light of the above, GPU Nuclear will not be able to complete the modifications by cycle 10/11 refueling outage (scheduled to start in 1984) as stipulated in 10 CFR 50.48.

Therefore, we are requesting that the date required for completion of the alternate s hu tdc,wn systems be extended to cycle 11/12 refueling outage (tentatively scheduled to start in 1987).

With respect to other Appendix R III.G modifications, because of our present workload and the fact that sc.e of the modifications will require the plant to be shutdown in order to be installed, we are requesting the following schedule exemption be granted:

all modifications that do not require a plant shutdown will be completed by December 31, 1984, all modifications requiring the planc to be shutdown wtll be completed before th e startup from our cycle 10/11 outage presently scheduled to begin in late 1984.

Delaying th e implementation of the subject Appendix R requirements will not result in undue risk to the health and safety of the public because of the existing upgraded fire protection system at the plant and because the available shift manning ensures sufficient personnel are available to shutdown the plant with the existing facilities.

Enclosure No.

5 of th is letter provides a list of exemptions from the hardware requirements of 10 CFR 50.48.

fue information contained in this submittal is correct to the best of our knowledge.

Additional information to that contained in this submittal will be provided, if required, to support your review and approval of the subject modification.

If, during the development of th e detail design, we determine th a t additions, changes, updates or corrections are needed, we will notify you of such.

~.

Mr. Dennis M. Crutchfield Page 3 June 30, 1982 If additional information or clarification is required, please contact Mr.

J. Knubel a t (201) 299-2264.

Very truly yours, f) l Peter'B. Fiedler Vice President and Director Oyster Creek PBF:JK:rss Enc losu re s :

1.

Fire liazards Analysis, Appendix R Fire Evaluation Report 2.

Fire liazards Analysis Report 3.

Alternate Shutdown Capability Procedure Guidelines 4.

10 CFR 50 Appendix R Modifications Schedule 5.

Exemptions from the liardware Requirements of 10 CFR 50.48 cc:

Mr. Ro nald C. Ila yne s, Ad minis tra tor Region I U.S. Nuclear Regulatory Commission 6 31 Park Avenue King o f Prussia, PA 19406 NRC Resident Inspector Oyster Creek Nuclear Generating Station Forked River, NJ 08731

  • e ENCLOSURE t/3 OYSTER CREEK ALTERNATE SHUTDOWN CAPABILITY PROCEDURE GUIDELINES Proceduro Guidelines - Safe Shutdown From Outside the Control Room Plant procedures will be developed which will direct the operators in the tasks to be performed to achievo and maintain hot shutdown from outside the control room with or without offsite power, and to subsequently come to cold shutdown. The existing plant procedure titled " Fire in the Control Room" is not sufficient for this purpose and will be replaced.

The following is an outline of the shutdown procedures:

1.0 When a decision is made to evacuate the control room due to a fire in the control room or cable spreading room, operators will attempt to complete the following actions prior to evacuating the control room:

1.1 Scram the reactor and close MS1V's.

1.2 Trip feedwater pumps.

1.3 Trip recirculation pumps.

1.4 Put isolation condenser B into service.

1.5 Verify all rods are in and the reactor is subcritical.

1.6 Trip the turbine.

2.0 Operators will remove all portable radios from the control room and shift supervisors office and proceed to assigned locations at the remote shut-down panel and transfer switches.

3.0 Remote shutdown panel controls will be activated by operation of the transfer switches and the action will be confirmed at the remote shutdown panel.

4.0 Steps 1.1 through 1.4 above will be confirmed or will be performed at the remote shutdown panel if not completed prior to evacuating the control room.

Reactor suberiticality will be confirmed using remote shutdown panel neutron monitoring instrumentation.

5.0 Operate isolation condenser B to maintain reactor pressure below 1000 psig.

Do not exceed a 100*F/hr cooldown rate.

6.0 Locally confirm proper operation of the diesel generators if required by loss of offsite power.

7.0 Avoid reactor vessel inventory loss through low pressure systems by closing and maintaining closed the following valves:

7.1 Cleanup system isolation valves.

7.2 Core spray parallel valves or test valves.

~

h ENCI.0SURE #3 (Contd) 8.0 Operate the CRD hydraulic system to maintain reactor water level above the low level scrau setpoint and below the bottom of the ise,lation condenser steam line.

9.0 Makeup to the isolation condenser shell as required to keep the water level above the top of the isolation condenser tube bundles by locally starting a condensate transfer pump and operating the isolation condenser makeup valves from the remote shutdown panel or locally. If condensate water is exhausted, locally valve in fire protection water to the IC shells.

10.0 Reestablish drywell cooling by starting the drywell recirculation fans, one reactor building closed cooling water pump, and one service water pump locally.

11.0 To come to cold shutdown:

11.1 Operate an isolation condenser to reduce reactor temperature to below 350*F (pressure below 120 psig) at a cooldown rate not to exceed 100*F/hr.

11.2 Start a second reactor building closed cooling water and service water pump locally.

11.3 Close the E recirculation loop discharge or suction valve locally.

11.4 When offsite power is available, align the shutdown cooling system valves and start two pumps locally.

11.5 Control the cooldown rate by throttling the shutdown flow locally to keep the cooldown rate below 100*F/hr.

11.6 Continue cooling down until the reactor temperature is maintained below 212*F.

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1. THis PorCOC CD PL AN FCA MDCIFICATIONS IMPLEMENTING ICCFR50, APPENDtX R, IS DEPENDA!1T C'. ' 'C ACCEPTA*. E CF THE UPDATED CYSTER CREEK FIRE HAZ ARDS Af;ALYC:3 'Tre ;T ONCLUNG THE AF PENDix R EV ALUAT:C'3. THE PROPOSED PLAN ASSU?.'ES f.RC AffiiUVAL Or THE I CCFR50 APFEf 4DtX R PROGRAM WITHOUT CHANCE IN SCOPE.

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2. CYCLE 9/ t C OJT AGE IS SCHEDULED TO START JANUARY I 5,1983. Aff9 IS EXPECTED EtiGINEERING TO Ef 0 BY DECE EER 31. I SS3. CYCLE 10/ I I OUTACE IS SChENLED TO START IN TC 4th CU ARTER CF 1984 AND IS EXPECTED TO LAST 9 frNTHS. CYCLE I 1/12 OTHER f.elLESTONES OUT AM 13 FFCTED TO ST ART If4 THE I st OUARTER OF 1987 DURATION IS f40T 9

AS INDICATED DCTER:.'J i D i ET

3. NPC APPPOVAL YUST BE RECElVED DY THIS DATE TO ALLOW IMPLEMENTATION F

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N Exemptions f rum the Hardware Requirements of 10 CFR 50.48 Exemptions are required for the below listed areas from the requirement of providing additional automatic fire suppression / detection when 1-hour barriers are utilized.

The specific justifications for these exemptions are provided in Section 5.0 of the "0yster Creek Nuclear Cenerating Station Appendix R Fire Evaluation Report."

!!owever, in general the justifications for the exemptions are based on the low combustible loading in each of the areas and the other fire protection features that are already inplace within each area.

Fire Area / Zone Anticipated De si;m a t i oa Description

!!od i fi ca t ion s FZ-1B Reactor Building, elevation 95' I or 2 FZ--1 C Reacter Luildind, elevation 75' 1 or 2 FZ-lD Reactor Euilding, elevation 51' I or 2 FZ-lE Reactor Building, elevation 23' 1 or 2 FZ-lF Reactor Euilding, elevation 19' 1 or 2 FA-3A IC 4160V Emergency Switchgear 1 or 2 Vaults FA-6 Switchgear Room 1 or 2 FZ-SA t!G Set Room 1 or 2 FZ-8C A&B Battery Room, Tunnel and I or 2 Tray Roon F7. -10A Service Building, elevation 46' I or 2 FZ-100 Service Euilding 1 or 2 FZ-1IB Turbine Lube Oil Storage, Punping 1 or 2 and Purification Area FZ-llc Switchgear Room, west end of 1 or 2 Turbine Euilding on !!czzanine 1, eve l FZ-llD Basement Floor South end 1 or 2 FZ-llE Condenser Bay 1 or 2 FA-14 Circulating Water Intake 2

FA-19 Old Radwaste Building 1 or 2 1-Cable rerouting 2-P rov id e 1-hour protective barriers

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