JPN-92-018, Forwards Info Re Use of Low Pressure Sys to Achieve & Maintain Safe Shutdown Following Control Room Fire,Per Concerns Raised During Recent NRC Fire Protection Insp
| ML20100R534 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 04/10/1992 |
| From: | Ralph Beedle POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| JPN-92-018, JPN-92-18, NUDOCS 9204160180 | |
| Download: ML20100R534 (9) | |
Text
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123 Man Street WMe P!ains. New Yxk 10601 914 681 6846
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April 10,1992 JPN-92418 U.S. Nuclear Regulatory Commission Mail Station PI 137 Washington,DC 20555 Attn: Document Control Desk
SUBJECT:
James A. FitzPatrick Nuclear Power Plant Docket No. 50-333 Fire Protection Program Safe /Altarnate Shutdown Using Low Pressure Systems REFERENCES.
1.
NYPA letter, R. E. Beedle to the NRC, dated March 27,1992 (JPN 92-014),
regarding a schedule for the fire protection program.
Dear Sir:
During the recent NRC fire protection inspection at FitzPatrick, the inspection team raised a concem about the extensive use of low pressure systems to safely shutdown the c' ant in the event of a fire. Specifically, they were concerned that the use of only low pressure sysh,ms (Automatic Depressurization, Low Pressure Coolant injection and Core Spray Systems) to reflood the reactor could result in reactor water level dropping below the top of active fuel during the transition to safe shutdown. In response to this concern, the Authority committed to describe those conditions where low pressure systems wou!d be used in FitzPatilck's new Safe / Alternative Shutdown Analysis (Reference 1). Attachmern 1 provides this informatioq.
High pressure systems will be available to safely shutdown the piant in thirteen of twenty fire -
areas. No core uncovery will result in the event of a fire in any of these areas.
The information in Attachment 1 is based on the new analysis as it exists today. The Authority is working to determine what modifications can be installed to make high pressure systems avallable in more areas. Analyses are being done to detemune the minimum reactor water level when low pressure systems are used. No exemptions are being requested at this time. Any exemptions necessary as a result of this new analysis will be submitted separately.
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C If you have _any questions, please contact Mr. J. A._ Gray, Jr.
Very truly yours, _
e-Ralph E. Beedle Executive Vice President Nuclear Generation cc:
Regional Administrator U. S. Nuclear Regutatory Commission
~475 Allendale Road-King of Prussia, PA-19406 -
Office of the Resident Inspector U. S. Nuclear Regulatory Commission PO Box 136 Lycoming, NY 13003 Mr. Brian C. McCabe Project Directorate 11 Division of Reactor Projects-1/11 U.S. Nuclear Regulatory Commission Mail Stop 14 B2-Washington, DC 20555 j
' to JPN 92-018 New York Power Authority James A. RtzPatrick Nuclear Power Plant -
USE OF LOW PRESSURE SYSTEMS TO ACHIEVE AND MAINTAIN SAFE SHUTDOWN FOLLOWING ACONTROL ROOM FIRE Introduction Durinq the recent NRC fire protection inspection at RtzPatrick, the inspection team raised a concem about the use of low pressure systems to safely shutdown the plant when the fire does not require operators to evacuate the Control Room. Specifically, they were concerned that the ~
use of only low pressure systems (Automatic Depressurization, t.ow Pressure Coolant Injection -
and Core Spray _ Systems) to reflood the reactor could result in reactor water level dropping below the top of active fuel during the transition to safe shutdown. In response to this concern, the -
Authority committed to describe those conditions where low pressure systems would be used in
. FitzPatrick's new Safe /Altemative Shutdown Analysis (Reference 1). This attachment provides-this information.
Changes from 1985 Safe / Alternate Shutdown Analysis !
Tnere are six fire areas where the system relied on for safe /a!tarnate shutdown has changed from the 1985 to 1992 analyses.- In three of these fire areas (ID, XI and XV) the Authority is proposing to =
use low pressure systems instead of high pressure systems used in the 1985 analysis. In two fire areas (Il and IV), high pressure systems are being used instead_of the low pressure systems. And, in one fire area (IA) a different high pressure system is being used. High pressure systems wil! be available in at least thirteen of the twenty fire areas.
These changes are summarized in Table 1. Table 2 lists the systems used to achieve and. maintain safe shutdown in the 1985 and 1992 Safe / Alternate Shutdown Analyses.' Table 3 describes the -
twenty fire areas at FitzPatrick.
I
' to JPN-92-018 TABLE 1
SUMMARY
OF CHANGES FROM 1985 TO 1992 FITZPATRICK SAFE / ALTERNATE SHUTDOWN ANALYSIS FIRE AREA
SUMMARY
OF CHANGE lA The 1992 reanalysis uses HPCI instead of RCIC to achieve and maintain tafe shutdown.
ID The 1992 reanalysis uses ADS /LPCI instead of HPCI to achieve and maintain safe shutdown.
11 The 1992 reanalysis uses RCiC instead of low pressure systems (ADS /LPCI or ADS /CS) to achieve and maintain safe shutdown.
IV The 1992 reanalysis uses RCIC instead of low pressure systems (ADS /LPCI or ADS /CS) to achieve and maintain safe shutdown.
XI The 1992 retaalyses uses ADS /LPCI instead of RCIC to achieve and maintain safe shutdown.
XV The 1992 reanalyses uses ADS /LPCI instead of HPCI or RCIC to achieve and maintain safe shutdown, l
Abbreviations used in table:
i HPCI = High Pressura Coolant injection LPCI = Low Pressure Coolant injection ADS = Automatic Depressurization System
. CS = Core Spray System RCIC = Reactor Coolant isolation Cooling l-m
' to JPN 92 018 TABLE 2 HOT SHUTDOWN (HSD) SYSTEMS USED IN 1985 AND 1992 FITZPATRICK SAFE / ALTERNATE SHUTDOWN ANALYSES FIRE AREA 1992 HSD SYSTEM"*
1985 HSD SYSTEM IA HPCI RCIC IB HPCI HPCI IC HPCI HPCI ID ADS /LPCI HPCI IE RCIC RCIC 11
' RCIC Low Pressure
HPCI HPCI
?
VI RCIC RCIC VII ADS /LPCI ADS /LPCI Vlli RCiG -
RCIC IX Low Pressure Low Pressure X
Low Pressure Low Pressure XI ADS /LPCI RCIC Xll RCIC RCIC XIll HPCI HPCI XIV HPCI HPCI XV ADS /LPCI-HPCI or RCIC XVi*
- New Fire Area (Battery Room Corridor) added in 1992 analysis.
- A low pressure system will be available in all areas.
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. to JPN-92-018 TABLE 3 FITZPATRICK FIRE AREAS / ZONES FIRE AREA FIRE ZONE AREA DESCRIPTION IA AD-1 Administration Bldg. el. 272-0 AD-2 Administration Bldg. el. 272-0 AD-3 Administration Bldg. el. 272-0 AD-4 Administration Bldg. el. 286-0 AD5 Administration Bldg. el.2864
..D-6 Administration Bldg. el.3004 AS-1 Auxiliary Boiler Rm. e!. 272-0 MG1 Motor Generator Rm. el. 300-0 IB FP-1 Diesel Fire Pump Rm. el. 272-0 CR-2 Radwaste Bldg. Control Rm. el. 284-0 RW1 Radwaste Bldg. and Pipe Tunnel SH 13 Screen Well Hcuse IC CT-1 Cable Tunnel West el. 260-0 SW 1 Switchgear Rm. el. 272 0, Turbine Bldg.
ID CT-4 Cable Tunnel 4 ci. 286-0
^
IE FP-2 Foam Rm. el. 272, Turbine Bldg.
TB 1 Turbine Bldq. (Basement) el. 2524, Mezzanine. 292-0 and Operating Fl. El 300-0 OR1 Turbine Oil Storage Rm. el. 252-0, Turbina Bldg.
OR-2 Turbine Oil Storage Rm. el. 272-0, Turbis 3 9bg.
OR-3 Misc. Oil Storage Rm. el. 272-0, Turbine % kj.
11 CT-2 Cable Tunnel E
- I el. 260-0 SW 2
' Switchgear Rm. el. 272-0, Turbino Bldg.
til BR-1 Battery Rm.1 el. 272-0 BR-2 Battery Rm. 2 el. 272-0 IV BR-3 Battery Rm. 3 el. 272-0 BR-4 Battery Rm.4 el. 272-0
'Attachmer 1 to JPN-02-018 k
TABLE 3 (cont'd) b FITZPATRICK FIRE AREAS / ZONES -
i FIRE AREA FIRE ZONE AREA DESCRIPTION V
EG-1 Emerg. Diesel Gen. Rm. el. 272-0 EG-2 Emerg. Diesel Gen. Rm. el. 272-0 EG-5 Emerg. Diesel Gen. Swgr. Rm. el. 272-0 VI EG-3 Emerg. Diesel Gon. Rm. el. 272-0 EG-4 Emerg. Diesel C ?n. Rm. el. 272-0 EG4 Emerg. Diesel Gen. Swgr. Rm. el. 272-0 Vil CR1 Mair' Coni 'ol Rm. 01. 300-0 RR1 Relay Rm. el. 284-0 CS1 Cable Spreading Room el. 272 Vill RB 1C Reactor Bldg. ol. 300-0 NE snd NW quadrants IX
_ SB 1 Standby Gas Filter Rm. el. 272-0 RB-1E Crescent Area East el. 227 0, Reactor Bldg.
RB 1 A Reactor Bldg. el. 272-0, east side, el. 3000 (SE quadrant) and entire el. 326-0,344-0, and 369-0.
X RB 1W Crescent Area West el. 2724, Reactor Bldg.
RB 1B Reactor Bldg. el. 272-0 west side and el. 300 0 SE;
- quadrant XI-
' CT Cable Tunnel 3, el. 286-0 Xil -
SP1 Servico Water Pump Rm.
X111 SP-2 Service Water Pump Rm.
XIV PC-1 Primary Containment (Drywell)
XV SU-1 Torus Area XVI BR-5 Battery Rm Corridor el. 2724 -
Attachrnent 1 e 'PN-92 018.
p Potential For Core Uncovery Using Low Pressure Systems -
4 RtzPatrick currently has an exemption from Appendix R to 10 CFR 50 that perrnits water level to briefly drop belo'v the top of active fuel during depressurization and reflooding using alternate safe shutdown, in the event of a fire in the Control Room / Relay Room / Cable Spreading Room (Fire Area Vil, Reference 2).- The new RtzPatrick Sale / Alternate Shutdown Analysis takes full credit for.
this exemption.
The Authority is preparing analyses to determine if reactor water level will drJp below the top of active fuel during the transition to safe shutdown for fires in areas where high pressure systems are not avaliable. Preliminary analysis indicate that the core will not be uncovered in the event of a -
fire in Fire Areas IX, X and XV. For the remaining areas, any core uncovery is expected to be less severe than that experier'ced for a fire in Fire Area Vil (Control Room / Relay Room / Cable Spreading Room).
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. to JPN 92-018 Referencsc 1.
flYPA letter, R. E. Bea.dle to the NRC, dated March 27,1992 (JPN-92414), regarding a t,chedule for the fire protection program.
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2.
NRC lottor, R. M. Bernoro to J. C. Brons dated September 15,1986, rogarding an exemption from Appendix R to 10 CFR 50 concerning core uncovery during alternative shutdown.
3.
NRC lotter, D. B. Vatts'io to J. P. Bayne dat9d July 1,1983, regarding exemption requests -
t0 CFR 50.48 Fire Protection and Appendix R to 10 CFR 50.
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