ML20054K494
| ML20054K494 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 06/28/1982 |
| From: | Daltroff S PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | Eisenhut D Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20054K495 | List: |
| References | |
| GL-81-12, NUDOCS 8207020254 | |
| Download: ML20054K494 (2) | |
Text
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PHILADELPHIA ELECTRIC COMPANY 23o1 M ARKET STREET P.O. BOX 8699 PHILADELPHI A. PA.191o1 SHIELDS L DALTROFF ELtctscPm o CTrom June 28, 1982 Docket Nos. 50-277 50-278 Mr. Darrell G.
Eisenhut, Director Division of Licensing US Nuclear Regulatory Commission Washington, DC 20555
SUBJECT:
Peach Bottom Fire Protection t
Safe Shutdown Report
Dear Mr. Eisenhut:
t t
This letter transmits the Peach Bottom Fire Protection Safe Shutdown Report that we committed to in our March 20, 1981, letter (S.
L.
Daltroff, Philadelphia Electric Company to D. G.
Eisenhut, N RC ), as amended by correspondence dated February 18, 1982 (S.
L.
Daltroff to D.
G. Eisenhut).
The study responds to the safe shutdown capability criteria presented in 10 CFR 50, l
Appendix R,
Section III.G. 2, and Generic Letter 81-12, dated February 20, 1981, as clarified by your letter dated May 4, 1982 l
(M.
B.
Fairtile, NRC to E.
G. Bauer, Jr.,
Philadelphia Electric Company).
l The information to be supplied in the report as it relates to l
alternative shutdown methods was outlined in correspondence dated June 3, 1981 (J. W.
Gallagher to D.
G. Eisenhut).
We have subsequently elected to implement appropriate modifications to I
comply with the separation criteria of Section III.G.2, or l
provide technical justification for exemptions to that criteria, in lieu of alternative shutdown systems.
Consequently, the format of the report has been restructured to conform with the l
proposed modifications, and the clarification provided in the May 4,
1982 letter previously ~ eferenced.
8207020254 820628
/ 0gh PDR ADOCK 05000277 f
F PDR L
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Mr. D. G. Eisehut, Director Pago 2 i
To expedite your review of the enclosed report, we propose informal work sessions and plant inspections, scheduled at your convenience, between the NRC reviewers and our techriical staf f.
Marked up drawings would be available to assist in the review process at these meetings.
Schedules to achieve compliance as required by 50.48(c)(5) are identified in Section 5 of this report.
Modifications necessary to comply with the separation criteria of Section III.G.2 of Appendix R are tabulated in Section 6.
Exemption requests pursuant to 50.48(c)(6) are identified in Section 3.
Should you have any questions regarding this matter, please do not hesitate to contact us.
Very truly yours, i
/
/
/r
.?
Q Enclosure i
cc:
C. J. Cowgill, Site Inspector i
4 1
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0 1
FIRE PROTECTION t
SAFE SHDTDOWN REPORT i
i Peach Bottom Atomic Power Station Units 2 and 3 e
Docket Nos. 50-277 and 50-278 Philadelphia Electric Company 4
June, 1982 O
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f TABLE OF CONTENPS 1
l Section 1 Introduction i
Section 2 Safe Shutdown Analysis Room Survey i.
Section 3 Supplemental Infonnation and Exemp-
~
tion Requests i
j Section h High-Low Pressure Interface Analysis t
Section 5 Associated Circuits Analysis i
Section 6 Tabulation of Modifications Appendix Architectura? Drawings
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l SECTION 1 i
Introduction I
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Peach Botton Atomic Power Station Units 2 and 3-Safe Shutdown Analysis Section 1 Introduction The Safe Snutdown Analysis was performed in accordance with the criteria and methodology contained in Enclosure 1 to the letter from J. W. Gallagher to D.
G.
Eisenhut dated June 3, 1981, with a few exceptions that are identified below.
The two methods as described in that letter are as follows:
Method A The RCIC system is used to supply makeup water to the reactor from the condensate storage tank.
The RCIC system also removes energy from the-reactors in the form of steam used to drive the RCIC turbine.
Initially, as steam is generated at a rate in excess of RCIC consumption it is relieved to the torus by actuation of the relief valves. Heat is removed from the torus by one loop of the RHR system operating in the suppression pool cooling mode.
Torus water is circulated through the RHR heat exchanger and returned to the torus. Heat is removed from the RHR heat exchanger by the'HPSW system which in turn dissipates heat to the river
()
At a reactor pressure of 100 psig, the RCIC system becomes inoperative-due to system isolation. The reactor can then be depressurized below 75 psig by operation of the relief valves in the depressurization mode.
When.the reactor has been depressurized below 75 psig, the RHR system can be transrerred from torus cooling to the shutdown cooling mode.
In the shutdown cooling mode, heat is removed from the RHR heat exchanger by the HPSW system, which in turn dissipates heat to the river. The shutdown cooling mode of RHR will maintain the reactor in a cold shutdown condition.
Method B This method is essentially identical to Method A except that the.HPCI system is substituted for the RCIC system.
Following is a listing of exceptions and clarifications to the June 3, 1981 submittal reterenced above.
1)
Several areas of the plant were identified that contained cables and equipment for both methods of safe shutdown. For four of these areas, a third method of safe shutdown has been identified that uses equipment and cables that are not contained within these zones.
The description of the third safe shutdown method is included in the text description of these fire areas (fire areas 21, 29, 61 and 64) presented in Section 3 of the report.
O 1-1 e
T 2)
The instrumentation listed in the submittal was not included in the
-)
safe shutdown analysis. The reason for this and the modifications to permit compliance are included in Section 3 of the report.
3)
For purposes of the analysis, during the transition from hot shutdown to cold shutdown (Reactor vessel depressurization from above 100 psig to below 75 psig using Safety Relief Valves) make up water to the vessel can be supplied from the RHR system that is in torus cooling for hot shutdown and will be lined up for shutdown cooling in cold shutdown. The equipment necessary to provide this make up capability has been included in the Safe Shutdown Analysis.
4)
The equipment required to be functional to get to cold shutdown is the same as that required for hot shutdown with the exception of the use of relief valves for depressurivation (method B only) and the RHR shutdown cooling isolation valtes (MO 10-17 and MO 10-18).
These isolation valves must be opened to get into cold shutdown.
The MO 10-17 valve can be accessed and manually stroked.
The MO 10-18 valve, and the relief valves are inside containment; due to the inerting of containment, the equipment inside containment will not be subject to a fire.
However, the power and control feeds for these valves outside containment could be damaged during the fire.
If this occurs the power and control cables for these valves may have to be repaired.
Sufficient cables to effect these repairs will be raintained on site along with precedures to accomplish these repairs.
O 5)
The FCIC system will be controlled from the remote shutdown panels.
This will allow the evacuation of the control room, if required, and minimizes the cables to be tracked, for purposes of the Safe Shutdown Analysis, in the control room and cable spreading room.
6)
Both Methods A and B assume that the SRV's do not operate spuriously.
To support this assumption, the control and power cables for the SRV's whose fire induced failure could cause their spurious opening will be encapsulated within their own rated fire bcrrier. This will assure that these valves will either not open from a fire outside the encapsulation or that, for a fire within the encapsulation, there will be no other fire damage coincident with their spurious operation.
7)
There were a few control and power cable design deficiencies identified during the initial stages of the Safe Shutdown Analysis.
Since it was apparent that these cables would have to be corrected for other reasons, these controls were not tracked as Safe Shutdown cables. The modifications to correct these deficiencies are included in the Safe Shutdown modifications identified in Section 5.
Whenever any of these situations were discovered that had licensing concerns, the concerns were corrected or justification was made to f-provide continued operation.
U 1-2
fs Section 2 of this report preser.ts the results of the Safe Shutdown Analysis for each fire zone in the plant. The format of the report is as follows:
Fire Area / Zone - The number indicates a number assigned to a specific fire The letter indicates a specific zone within the numbered fire area.
area.
These fire zones correspond to the ones identified in the Peach Bottom Fire Protection Program Report dated March 1977.
The barriers between fire zones will be upgraded to provide the necessary isolation between the two methods of safe shutdown as required.
Description - Identifies the major equipment in the fire zone.
Elevation - Provides the floor elevation of the lowest room in the zone.
Identifies the shutdown method or nethods involving safe SS Equipment shutdown equipment found in the fire zone.
Room Number (s) - Identifies the room numbers (from the Architectural Prints submitted in the Fire Protection Program Report March 1977) of the rooms contained within the fire zone.
An asterisk indicates that there are more than three rooms within the zone.
Refer to the Fire Protection Program Repdrt for the complete listing of rooms within the fire zones.
A set of Architectural Prints from that report is enclosed for reference.
()
Comments - Fire zones that contain equipment and cables for both shutdown methods are the only zones that have comments regarding modifications to ensure compliance with Section III.G.2 criteria, or identifying exemption requests pursuant to 10CFR50.48 along with a technical basis that provides assurance that a fire in the Fire Zone would not effect equipment and cables for all safe shutdown methods.
Zones marked with a double asterisk and exhibiting the comment " Refer to text" have additional comments presented in Section 3.
The fire zones without comments are in compliance with 10CFR50, Appendix R,Section III.G.2 separation criteria.
Whenever the terms " rerouted" or " encapsulated" are used in the report, the rerouting or encapsulation will provide full compliance with the requirements of Section III.G.2.
Any rerouting will remove the offending cables from the fire zone and will place them in a fire zone assigned to that Method.
Any encapsulation will either be with a three hour rated fire barrier when no automatic suppression system exists in the area or with a one hour rated fire barrier if a suppression system exists or is added to the area.
The high-low pressure interface criteria and associated circuits criteria are analyzed in Sections 4 and 5 respectively, as requested in attachment 2 to enclosure 2 of the May 4, 1982 letter (M. B. Fairtile, NRC to E.
G.
- Bauer, Jr.,
PECO).
Section 6 tabulates all the modifications identified in this report.
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SECTION 2 Safe Shutdown Analysis Room Survey O
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SECTIG4 2 - SAFE SHUT 00144 AtlAL POOM Stt?1ARY 06/25/82 PEACH BOTTOM ATCt1IC F0WER STATION LHITS 2 AND 3 1
FIRE ZOffE:
1 DESCRIPTI0ti: UNIT 82 2A RHR k
ELEVATI0ti : 91 SS EQUIFttENT: NETH00 A R00t1 tlUt1BER(SI: 2,101 FIRE 20t!E:
2 DESCRIPTI0ti: LR4IT#2 2C RHR Cf)
ELEVATI0tl : 91 8
SS EQUIPMENT: NotlE yw ROOM 11 UMBER (SI: 3,102 g
FIRE ZONE:
3 DESCRIPTI0ti: tA4IT32 2B RHR ELEVATI0tl : 91 SS EQUIPMENT: NETHOD B ROCt1 i:Ut1BER( S ): 4,103 FIRE 20ttE:
4A DESCRIPTI0ti: LRIITS2 20 FHR ELEVATI0t1 : 91 SS EQUIPt1ENT: HONE ROct1 HUttBER(S): 5,104
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SECTI0tf 2 - SAFE SHUTDOWN AHALL. ROOH SUtttARY 06/25/82 U
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PEACH COTTON ATONIC FOWER STATION tNITS 2 AtO 3 2
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FIRE ZOtlE AB C0tttENTS: FIRE RATED BARRIER TO BE BUILT AROUte it0 TOR Cot 3 TROL CEllTER '
20011. TWO CADLES TO BE REROUTED, Atc EIGHT C0tIDUITS TO BE EHCAPSULATED TO ESTABLISH THIS ZCttE AS A NETHOD
B" ZollE. AN AUT0ttATIC DETECTION 1
DESCRIPTI0ts: UNITW2 REACTOR At1D SUPPRESSI0tt SYSTEtt CURRENTLY EXISTS IN THIS ZCtlE.
BLDG. COOL. WTR.
R00t1 ELEVATI0tl : 116 SS EQUIPttENT: NETit03 A,B RC0t1 ffUttBER(S): 105 FIRE ZONE:
4C CONNENTS: CABLES NEED TO BE REROUTED WITHIH THEIR 024 COtOUITS BEFORE SEPARATIC'1 IS PROVIDED. THEN HALF OF THE SAFE SHUTDOW4 CABLES IN THE 20t4E (OttE NETHOD OF SAFE SHUTDOWN CABLES) WILL BE Et1CAPSULATED DESCRIPTIOH: UNITW2 2AAB REACTOR TO PROVIDE THE HECESSARY ISOLATIOll. AN AUTCHATIC DETECTION AND SUPPRESSION RECIRC. PUttP ttG SYSTEtt CURRENTLY EXISTS IN THIS ZONE.
1 ELEVATIOtl : 135 i
SS EQUIPHENT: NETHOD A,B RC0tt t#Ut1BER(S): 206 FIRE 20t1E:
5A DESCRIPTI0ti: UtlITW2 2C CORE SPRAY ELEVATI0H : 91 SS EQUIrrtENT: NETif00 A ROC tlUttC ERI S ): 11 1
FIRE ZONE:
5B i
DESCRIPTION: tR11T32 2A CORE SPRAY ELEVATI0tl : 91 i
l SS EQUIrt*ENT: H0HE R00t1 HUttBER(SI: 12 c
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06/25/82 s
FEACH BOTTON ATot1IC POWER STATION LNITS 2 HIO 3 3
FIRE ZOffE:
SC C0tttENTS:
- -EXEMPTION REQUESTED BASED ON EXTEttSIVE SEPARATI0ti BETWEEN REDUllDANT EQUIPMENT At!D LACK OF INTERVEHIt4G CCISUSTIDLES. REFER TO TEXT.tSECTICH 31 DESCRIPTION: UNIT 82 TORUS COMPARTHENT ELEVATION : 91 SS EQUIPt1Elli: NETH00 A.B R00t1 tu1BERtS1: 1 FIRE ZONE:
50 DESCRIPTION: UNIT #2 2D CORE SPRAY ELEVATION : 91 SS EQUIPffENT: NETHOD B R00tf hut 2ER(S): 9 FIRE ZOt1E:
SE CONNENTS: THE "A" NETHOD CABLE (ZD2Q1024K) IN THIS ZONE TO BE REROUTED TO ESTABLISH THIS ZONE AS A NETHOD "B" ZCHE.
i DE*CRIPTION: UNIT 32 2D CORE SPRAY i
ELEVATION : 91 SS EQUIP! TENT: NETHOD A,B I
ROCM tM SER(SI: 10 1
FIRE ZONE:
5F l
DESCRIPTION: UNIT 32 INSTRUt1ENT RACKS ELEVATION : 116 SS EQUIrrtEHT: NETHOD A 1
4 R00t1 hut 2ER(S1: 108 i
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FEACH BOTTCt1 ATOMIC F0WER STATIC 4 tJ3TTS 2 At0 3 4
FIRE 20tlE:
EG Cot 1MENTS: THE "A" METHOD CABLE (ZD2Q1024K) Itl THIS ZONE TO BE REROUTED TO ESTABLISH THIS ZONE AS A METHOD "B" ZOt:E.
DESCRIPTI0ti: UNIT 22 IttSTRUMENT RACK ELEVATI0tl. 116 SS ECdJIPMEtTT: METHOD A,B ROOM ttUMBERIS): 107 FIRE ZONE:
5H COMMEtiTS:
- -EXEMPTI0tl REQUESTED B ASED ON FHYSICAL ARRAttGEMENT OF 20tlE. REFER TO TEXT.(SECTI0t3 3)
DESCRIPTI0tt: UttIT22 GENERAL AREA REACTOR BLOG.
ELEVATICH : 135 SS EQUIFt1Et4T: METHOO A B ROCM I:UMBERIS1: 205,212.209 FIRE 20t!E:
SJ COMMENTS:
- -EXEMPTI0tl REQUESTED BASED Ott PHYSICAL SEPARATI0tl BETWEEtt REDUt DAtiT SAFE SHUTDOWH EQUIPMENT IN THE ZONE.
REFER TO TEXT.(SECTION 31 DESCRIPTI0ti: Ut1ITs2 GEtrERAL AREA REACTOR BLDG.
ELEVATION : 165 SS EQUIPMEt4T: METHOD A,B R00t1 HUMBER(S): 400,403 FIRE ZOt1E:
SK DESCRIPTICH: UNIT #2 GENERAL AREA REACT 02 BLDG.
ELEVATI0tl : 195 SS EQUIPMENT: NONE ROOM H'JMBERISI:
500,501,502*
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PEACH BOTTCM ATOMIC PC'.JER STATIG4 tE4ITS 2 At:0 3 5
l FIRE ZotIE:
5L DESCRIPTIcti: Ut4ITR2 SO'SCE STCRAGE 8 CALIERATICt1 R00tl
[LEVATICtl : 195 SS EQUIPt1ENT: tiONE R00t1 itut10ER( S I: 504 FIRE ZCt!E:
SN DESCRIPTI0ft: UtlITR2 DACKWASif RECEIVIllG TAtfK POCH I
ELEVATI0tl : 165 SS EQUIFttEtiT 1'Ot tE I
RCOM tlUttBER(S): 4I0,430 4
FIRE ZOt!E:
6 DESCRIPTI0ti: STAIRWAY #24 ELEVATI0f4 - 91
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SS EQUIPr*ENT: t!ONE J
ROON t:UttDER(S):
FIRE ZCt:E:
7 D E SCR Y PTI0ti: STAIRWAY #18 i
ELEVATION : 91 l
SS EQUIrttEt4T: tiot4E RCOM IJUt1BER(S):
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SUMMARY
06/25/82
,,j PEACH BOTTON ATOMIC POWER STATICC4 Ut4TTS 2 AtB 3 6
FIRE ZONE:
8 DESCRIPTI0f t: STAIRWAY #19 ELEVATIOli
FIRE ZO'!E:
9 DESCRIPTIOll: UtlIT83 30 RHR ELEVATI0ti : 91 SS EQUIPMENT: NETHOD B R00tl IMfDER t S I: 159.41 FIRE 20t1E:
10 DESCRIPTI0ti: UNIT 23 3D RHR E LEVATIOtt 116 SS EQUIPMENT: il0NE ROON IFJtiOERI51: 40,158 FIRE 70ttE:
11 DESCRIPTION: UNIT 23 3C RHR ELEVATION : 91 SS ECUIPt1ENT: ttETH00 A ROOM IMIDER(SI: 39,157
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SECTI0tt 2 - SAFE SHUTDOL31 ANALL ROOM SUt1 MARY 06/25/02 PEACH BOTTOM ATCMIC POWER STATIC l1 tP4ITS 2 Ato 3 7
FIRE 20ttE:
10A DESCRIPTI0ti: UttIT23 3A RHR ELEVATI0ti : 91 SS EQUIPttENT: H0tlE ROct1 tL'MBER(S): 38,156 FIRE ZONE:
128 CONNENTS: THE "B" HETH00 RACEWAYS IN THIS 20tlE (TRAY ZB3GV01 AND C0tCUITS ZB3P313. ZB3P314 ZB3P9101 TO BE Et:CAPSULATED TO ESTABLISH THIS 20t1E AS A NETHOD "A" ZONE. AN AUTONIC DETECTI0tt At0 SUPPRESSICH DESCRIPTION: UttIT23 REACTOR SYSTEN CURRENTLY EXISTS IN THIS ZONE.
BLDG. COOL. HTR.
ROOM ELEVATICH 116 SS EQUIPt1EtlT: NETHOD A.B ROOM HUMBER(SI: 162 FIRE ZCtlE:
12C CONMENTS: OtlE "B" METHOD CABLE (ZA3Q1827Al NEEDS TO BE REROUTED TO OTHER COtCUIT BEFORE SEPARATION IS PROVIDED. THEH HALF OF THE SAFE SHUTDOWN CABLES IN THE ZO!1E (C!!E MCTHOD OF SAFE SHUTDOWN CABLES) WILL BE DESCRIPTION: UNIT 83 ENCAPSULATED TO PROVIDE THE HECESSARY ISOLATION. AN AUT0t1ATIC DETECTION 3A13B RECIRC.
At0 SUPPRESS 10tl SYSTEN CURRENTLY EXISTS IN THIS ZONE.
ELEVATION : 135 SS EQUIPttENT: ttETHOD A.B ROOM hut 1 DER (S): 258 FIRE ZONE:
13A DESCRIPTION: Ut4ITE3 3B CORE SPRAY ELEVATI0tl 91 SS EQUIPttEtlT: it0ttE ROCH HUtfDER(S): 43
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SECTION 2 - SAFE SHUTDotN AtiAL ROON SUtttARY 06/Z5/42 PEACH BOTTON ATot1IC POWER STATI0il (NITS 2 Atm 3 8
FIRE 20tlE:
138 DESCRIPTI0ti: UNIT 33 3D CORE SrPAY ELEVATI0ta : 91 SS EQUIrt1ENT: NETH00 B RCott flu *iBERf SI: 42 FIRE ZONE:
13C C0ft1ENTS: **EXENPTION REQUESTED BASED ON EXTENSIVE SEPARATION BETWEEN PEDUtOANT EQUIPMENT AfD LACK OF IttTERVENIHG C0t100STIBLE. REFER TO TEXT.(SECTION 3)
DESCRIPTICH: UNIT 83 TORUS COr1PARTHEt4T ELEVATI0t1
- 91 SS EQUIPt1ENT: NETH00 A.B R00t1 ItuttBER( S I: 37 FIRE 20tlE:
130 C0tir1EHTS: THE "B" NETH00 CABLES IN THE ZONE (ZB3Q1794A.Bl TO BE REROUTED OR EHCAPSULATED TO ESTABLISH THIS ZONE AS A NETH00 "A" ZOt1E.
DESCRIPTI0ft: UttIT83 3C CORE SFRAY ELEVATI0tt : 91 SS EQUIPNENT: NETHOD A B RCatt HUPIDER(S1:
^4 FIRE Zet1E:
13E DESCRIPTIDH: UNITN3 3A CORE SPRAY ELEVATION : 91 SS ECUIPt1Ef1T NETHOD A P00t1 hut 1BER(SI: 45
SECTICH 2 - SAFE SHUTD0t#1 ANAL ROOM SUtttART 06/25/02 PEACH BOTTON ATOMIC PC JER STATICH tHITS 2 APO 3 9
FIRE ZOttE:
13F DESCRIPTI0tl* UttIT33 IllSTPut1Et(T PAG ELEVATI0t3 : 116 SS EQUIrt1EHT: METHOD B POOM hut 1BER(S): 160 l
FIRE 20 tie:
13G COMMENTS: THE "B" METHOD CABLES IN THE ZONE (ZB3Q1794A,B) TO BE REPOUTED OR Et4CAPSULATED TO ESTABLISH THIS ZO!!E AS A NETHOD "A" ZOtlE.
DESCRIPTI0tl: UtlITR3 IttSTRUMENT RACK ELEVATI0tl : 116 4
SS EQUIPMENT: t1ETHOD A,B ROCM IU1BER(S1: 161 FIRE 20 TIE:
13H COMMDITS:
- -EXEMPTION REQUESTED BASED Ott A PHYSICAL ARRANGEMENT ZONE.
REFER TO TEXT.(SECTI0ft 3)
DESCRIPTI0ti: (AlITs3 GEt!ERAL i
AREA REACTOR BLOG.
I ELEVATICH : 135 l
SS EQUIFt1EtiT: NETH00 A,8 ROOM fiUMBERIS): 250,252,257 4
FIRE ZONE:
13J C041ENTS:
- -EXEMPTION REQUESTED BASED ON PHYSICAL SEPARATION BETMEEN REDUNDANT SAFE SH'JTD0l#4 EQUIPt194T IN THE 20t4E. REFER TO TEXT, DESCRIPTION: UNIT 23 GENERAL AREA REACTOR DLOG.
1 ELEVATI0tl : 165 SS EQUIPMENT: NETHOD A,B POOM PU EERIS): 444,447 i
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06/25/82 POOM $Utt1ARY SECTICH Z - S AFE SHUTDouti AttAL 10 FEACH BOTTCM ATOMIC POWER STATI0ti LUITS 2 HC 3 i
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THE "A" t1ETH00 CABLES Itl THE ZO*1E TO BE REROUTED OR COtit1ENTS:
EttCAPSULATED TO FPOVICE REQUIRED SEPARATICt4.
f FIRE 20*iE:
13K f
l DESCRIPTICH: UtlIT23 GEt!ERAL l
APE A REACTCR l
BLOG.
I ELEVATICtl
- 195 l
SS EQUIPMEllT: t1ETHOD A.B l
ROON HUttCER(S):
517,518,514*
FIRE ZOt!E:
13L DESCRIPTICil: UtlIT23 SOURCE STORAGE ELEVATION
13t1 DESCRIPTIDH: Ut41T23 BACKWASH TAttK ROCN l
ELEVATICt1 165 l
SS EQUIrttEt1T: !!CttE POOM IRJtfDERIS): 452,453 FIRE 2Ct1E:
14 DESCPIPTI0ti: STAIRWAYt:5 ELEVATIOtt
- 91 SS EQUIP!1Et4T: 110tlE ROCM PFJtfjERIS1:
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SECTI0tl 2 - SAFE SHUTDotal AtiAL ROON StA1 NARY 06/25/82 PEACH EOTTON ATWIC POWER STATION LPIITS 2 Atm 3 13 FIRE 20tlE 23 l
h t>ESCRIPTI0ti: UNIT 32 CUTBOARD i
ISOL. VALVES i
i ELEVATI0tl : 135
}
j SS EQUIPt1ENT: NETH00 8 RCOM !!UtiBER(S): 204 j
FIRE 20t1E:
24 CONNEtiTS:.THIS AREA IS IHERTED DURING OPERATI0tl. THE "B" NETH00 EQUIPMENT (NOTOR OPERATED VALVESI IN THIS ZONE IS Iti ITS CORRECT OPERATItG FOSITI0tt Att0 A CADLE FAILURE cat #40T CAUSE THEN e
i DESCRIPTI0ft: UNIT 52 DRYWELL TO NOVE FRON THAT POSITION.
1 ELEVATI0tl : I35 1
SS EQUIPt1EtiT: NETHOD A,B 1
FOCN t1U'fBER(S): 202.401 i
FIRE 20tlE:
25 i
DESCRIPTI0t4: UNIT 52 C0fiTROL j
R00 DRIVES' 1
ELEVATIO!4 135 SS EQUIPt1ENT: Not:E i
POON t!UMBERt S): 201 FIRE 20tlE:
26 3
DESCRIPTION: STAIRWAY #26 i
j
)
ELEVATI0tl : 135 SS EQUIPMENT: H0HE i
R00t1 t!Ut BER(S):
s i
4 1
4
O c) n SECTIDH 2 - SAFE SHUTD0t#4 At!ALY.s. ROOM
SUMMARY
06/25/82 U
t PEACH ECTTCt1 ATOMIC 001 ER STATI0t4 t* LITS 2 AtM 3 I4 FIRE ZONE:
27 j
DESCRIPTIO'4: UNIT 33 OUTBOARD ISOLATION VALVES ELEVATI0H : 135 SS ECUIPMENT: NETH00 B P00t1 ffUtLEP(S): 249 I
FIRE ZCi1E:
28 f
s I
DESCRIPTICt4: Ut1ITs3 ORYWELL j
ACCESS HATCH i
I-ELEVATI0ti - 135 SS EQUIPMEt4T: 110tlE P00t1 I!UMDERI S I: 253 FIRE 20ftE:
29 CONNENTS:,**-THERE ARE TWO "A" NETHOD VALVES AND OttE "B" NETH00 VALVE IN THIS AREA. A DIFFERENT NETHOD OF SAFE SHUTD0bN CAN BE ACCOMPLISHED WITHOUT THIS AREA. REFER TO TEXT.lSECTION 31 DESCRIPTICH: UNIT 33 OUTBOARD ISOL. VALVES ELEVATI0H : 135 SS EQUIPt1EttT: METH00 A,B R00t1 HUMBER(S): 254 FIRE 20HE:
30 DESCRIPTION: UNIT 83 NEUTRON N0HITORItt3 SYSTEN ELEVATI0H : 135 SS EQUIPMENT: NONE ROON ttUtfBERiS): 255
_... -.. ~. -....., _..
-.- ~.- ~_--. -....
_,. ~. _ -..
SECTION 2 - SAFE SHUTD0544 AHALYaz - ROON
SUMMARY
06/25/82 PEACH BOTTON ATCMIC POWER STATI0H 03ITS 2 At40 3 15.
FIRE 20t1E 31 DESCRIPTI0ta: UHIT83 REACTOR WATER CLEAIAJP SYS. VALVES ELEVATI0tl : 135 SS EQUIPMEllT: NETH00 A ROCH HUTIBER(S): 248 FIRE ZOtlE:
32 CONNENTS: THIS AREA IS It!ERTED DURING OPERATION. THE "B" NETH00 EQUIPMENT (NOTCR OPERATED VALVES) IN THIS ZONE IS IN ITS CORRECT OPERATItfG POSITI0t1 AND A CABLE FAILURE cat #10T CAUSE THEN.
DESCRIPTION: UNIT 83 DRYWELL TO NOVE FROM THAT POSITI0tl.
1 ELEVATION ' 135 SS EQUIPMEHT: METHOD A,B ROOM HUttDERE S): 247,443 FIRE ZCtiE:
33 DESCRIPTICH: UNIT 83 CONTROL RCD DRIVES ELEVATI0tl : 135 SS EQUIPMENT: t10HE ROOM t! UMBER (S1: 246 FIRE ZCHE:
34 DESCRIPTION: STAIRWAY 527 ELEVATION : 135 SS EQUIPitEHT: H0tlE ROOM i:UttDER(S):
I
!a ex (j
(
)
kA)
SECTIOtt 2 - SAFE SHUTDOL54 AtlALY.$ ROOF 1 SUMt1ARY 06/05/02 FEACH BOTTOtt ATOMIC POWER STATIOt1 tRlITS 2 Ato 3 16 FIRE Zet1E:
35 DESCRIPTIOt4: Ut11T23 30 REACTOR WTR. CLEAT:UPt RWCU)
HEAT EXCHAt:GER ELEVATI0tl : 165 SS EQUIPMEtlT: t10t4E ROO!! IJUMBER( S I: 450 FIRE 20t1E:
36 DESCRIPTI0ft: UtlIT33 3A RbtU ELEVATIOtt : 165 SS EQUIPMEt1T: tot 4E R00t1tu ?JERIS): 449 FIRE 20tlE:
37 DESCRIPTI0t4* Ut4IT33 RWCU ELEVATI0tl
- 165 SS EQUIPMEt1T: tiotlE R00t1 ffUt10ERISI: 448 FIRE 20t1E:
38 DESCRIPTI0ft: UtiIT N 3 RbtU RECIRC.
ELEVATI0t1 : 165 SS EQUIFMEtlT: flotlE ROOM tiUMDER(S): toffE
V)
(A) o SECTIC;4 2 - SAFE SifUTDCuti At1ALYsd POOM
SUMMARY
06/25/82
\\j FEACH EDTTOM ATOMIC FCHER STATICt1 UtlITS 2 AtfD 3 17 FIPE ZOtlE:
39 DESCRIPTICti: UtIIT 83 3B RWCU PECIPC.
4 3
l ELEVATI0tl : I65 SS EQUIPt1EtiT: NotfE PCCt1 flu"SER(S): 446 FIPE ZCt!E:
40 DESCRIPTI0ti: UtlIT23 3A RWCU PECIPC.
1 ELEVATI0t1 : I65 SS EQUIPt1EliT: tiotJE PC0tt t1UttBERf S1: 445 FIRE 20tlE:
4I i
DESCRIPTIOti: Ut4IT82 2B RLTU RECIPC.
ELEVATI0tl : I65 SS EQUIFttEllT: t10t1E R00t1 tlUMBER(5): 409 FIRE ZC11E:
42 DESCRIPTI0ti: M4IT32 2A FWCU f
ELEVATI0t1 : I65 SS EQUIPttENT: HCtlE ROct1 HUMBERtSI: 408 4
.__m
______.m i
1
}
SECTION 2 - SAFE SHUTDOWN ANAL 4 R00rt SUtt1ARY 06/25/82 PEACH DOTT0t1 AT0t1IC POWER STATI0tl (NITS 2 H m 3 18 I
FIRE 20t!E:
43 i
j DESCRIPTI0ts: UNIT #2 RNCU
.I 1
ELEVATI0tl : 165 SS EQUIPt1EtiT: tele R00t1 trJMBERIS): 407 l
}
FIRE ZONE:
44 j
}
DESCRIPTION: UNITW2
{
2A RWCU RECIRC.
}
ELEVATI0t4 : 165 SS EQUIPt1EHT: HOttE l
ROCH hut 1BERIS): N0HE i
f FIRE ZOME:
45 DESCRIPTION: UNIT #2 1
28 RNCU RECIRC.
I;.
I ELEVATION : 165 SS EQUIP!1ENT: t04E 3
R00t1 hut 1BER(S): 405 FIRE ZONE:
46 l
1 DESCRIPTION: UNIT #2 g
1 2C RWCU RECIRC.
}
i I
ELEVATI0tl : 165 SS EQUIPt1ENT: POtE i
ROOH HUNDER(S): 404 i
i Y
k
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SECTION 2 - SAFE SHUTDOWH RHAL 3 R00tt SUMMApf C6/25/82 PEACH BOTTOM ATOMIC PCWER STATICH LP4TYS 2 A'O 3 20 FIRE 20tfE:
49 CCt1MENTS: THE FOUR C132 PANELS THAT CONTROL ECCS CD'fPART*'ENT COOLItG ARE LCCATED WITHIll THIS ZONE. TWO PANELS TO BC RELCCATED TO APOTHER FIRE Z0 tie.
DESCRIPTI0ti:
t, HITS 3 HVAC F ILTER COMPARTMENT ELEVATICtl - 195 SS E7JIFMEtfT: NETH00 A.B PCCM t!Ut1BER(S): 520.525.526*
FIRE 20tlE:
50 DESCRIPTI0ti: UNIT 83 HVAC FERS0ttlEL ACCESS AIRLCCK ELEVATI0tl
- 195 SS Er7JIrt1EtrT: tot 4E PCCM HUMBERfSI: ICriE FIRE ZC'4E:
51 COMMENTS: THE FOUR C132 PAtlELS THAT CCNTROL ECCS COMPARTMEN(
COOLItG ARE LOCATED WITHIN THIS ZOffE. TWO PAtlELS TO BE RELOCATED TO AtOTHER FIRE ZOt3E.
DESCRIPTICil: UNIT 82 HVAC FILTER CottrARTHENT ELEVATIC:4 : 195 SS EQUIrt1ENT: METHO3 A.B POOM IA!!fDER(S): 506.510.511a FIRE ZONE:
52 DESCRIPTIOP4: UNITR2 HVAC FERSottiEL ACCESS AIRLOCK ELEVATIcti : 195 SS EQUIPMENT: TONE RCCM i:UP1 DER (SI: totiC
(
v SECTIO 4 2 - SAFE SHtJTDCt.tl AttAL,
,) FOOrt SUMMARf 06/25/82 y/
FEACH EDTTON ATCttIC POWER STATI&4 (S8ITS 2 AtD 3 21 FIRE ZOt!E:
55 CESCRIPTIEti: LilIT83 FEFUELIt1G FLOCR ELEVATICt1 : 234 SS EQUIFMENT: tO4E FC0t1 tot *CER(SI: 519.611.613*
FIRE ZOt!E:
56 DESCRIPTICtt: 124I183 SatOWER ELEVATICtt : 234 SS EQUIrrtEt4T: PO4E POT t0HCER(SI: 612 FIRE ZOttE:
57 DESCRIPTICt4: Ut4IT82 PEFUELItC FLOCR ELF.VATIOil : 234 SS ECUIr:1Et4T : Hot 1E ROM tutBER(S):
507,601,603*
FIRE ZCt!E:
58 DESCRIPTIOti: (AIIT32 SHOWER ELEVATI0ft : 234 55 EC'JIPttEt4T: tele PC0tt t.tt1CERIS): 605
3 lI i
2 O)( 2 S
2 I
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SECTICil 2 - SAFE SNUTOCZ4 At2tt a FOOM '5UMMApr 06/*S/02
(,)
FE ACH ECTTCM ATOMIC FCWER STATIC;4
~
t* LITS 2 sto 3 23 FIPt ZCt:E:
63 CattENTS: THE SEVE'8 "B" METHC0 CABLES IN THE ZC'E TO EE PEROUTto Ct'TSICE CF THE ZCT!E CR ENCAFSULATLD TO ESTAELISH THIS ZCl ! AS A METHOD "A" ZCt.T.
DESC2IPTICt4: 13:IT33 PCIC TLTBIt!E 1 FtK!P ELEVATIC*l : 91 SS E 7)IN*!!!T : f*ETHC3 f.B FEM ?? *TEp( S I: 47 FIPE ZCt:E:
64 COttfEtiTS:
65 COMMENTS: THE "B" NETHOD CABLES IN THE 20t:E (ZP371799T. ZB3GIS00C.D.
ZA33Ia 7Al TO EE FERCUTED CR ENCAPSULATED TO ESTABLISH THIS ZCt:E AS A METH03 "A" ZCt!E.
CESCRIPTIC*4: SUMPS ELEVATIC*4
- 91 SS EC'JIrttEtiT: NETH00 A.B FC^M f:L*TEPfS1: 3I FIRE ZetlE:
66A DESCRIPTI0te: SOLID PADWASTE NASTE SLUDSE FUMP ELEVATICt1 : 91 SS ECUIPMEt!T: ta0NE PCCM t."JtTEPI S I: 06
^e\\
u d
tJ e2 Nm NN*a
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l 752 i
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SECTICtl 2 - SAFE SHUTDCM4 AttALL, ; R031 StJtt19Y c6/05/82 y'
FE ACH EOTTCit ATCt1IC FWER STATIC 4 (NITS 2 AO 3 25 FIRE ZCt:E:
6tB DE ECRIP TIO'4: T AtES ELEVATICil
- 91 SS EQUIrt1Et4T: t.'Ct E FCCM IfUMDERtS): 29 FIRE M 4E!
70 DESCRIPTI0ft: STAtODY GAS TREATMENT SYSTEM ELEVATI0?4 : 91 SS EQUlrt1ENT: METHOD B ROCit tu'DEPtSI: 33 FIRE 23;E:
71 DESCRIPTICil: STAIRMAY334 ELEVATI0tl : 91 SS EQUIrt1ENT: tt0ttE PCOtt hut 1 Dept SI:
FIRE 20t!E:
70A CCif1ENTS: **-EXEMPTI0t4 REQUESTED BASED ON LOW CONDUSTIBLE LOADING Atc MODIFICATION TO BE MADE TO FROVIDE ACCEPTABLE ISCLATICte.
REFER TO TEXT.4SECTICtl 3)
DESCRIPTION: ret 10TE SHUTDome pat:EL ELEVATICtl : 116 SS EQUIPMENT: NETHC0 A,B RCCitIUiDERESI:
142,143,154*
l SECTION 2 - SAFE SHUTDCW4 ANAL R00tt StkittARY 06/25/82 PEACH BOTTON ATONIC POWE2 STATICtl LHITS 2 Ato 3 26 FIRE ZONE:
72B DESCRIPTION: PUNPS ELEVATI0f4 : 116 4 evewe44-
)e** **',
SS EQUIPttENT: tat 4E ROCH HUticER(SI: 151.153.148 FIRE ZCtlE:
72C DESCRIPTIOt4: C0fDENSATE SLUDGE HIXING PUttP ELEVATION : 116 SS EQUIPNEHT: NETHOD A R00tf t?JHBER(SI: 147 FIRE ZONE:
72D C0t1ttENTS: THE "B" HETHOD CABLES IN THE ZONE (ZB3Q1799T ZB3Q1800C.D.
ZA3Q1827A) TO BE REROUTED OR EHCAPSULATED TO ESTABLISH THIS ZONE AS A NETH00 "A" ZONE.
DESCRIPTION: CottDEt4 SATE DENIN.
PHASE SEPARATOR TAttK ELEVATI0ft : 116 SS EQU1PHENT: NETHOO A,B POON PRROERIS1: 145 FIPE Z0tfE:
72E DESCRIPTI0ti: CCtOENSATE SLUDGE HIXING PUt1P ELEVATICH : 116 SS EQUIPMENT: NETH00 A ROCi1 HUtSERIS): 144 j
V SECTICt3 2 - SAFE SHUTD0'AH At3ALL,_, ; POCM Slit 1ARY 06/25/C2 FEACH COTTON ATCt1IC FUAER STATI0tt (71175 2 APU 3 27 FIRE ZOt:E:
72F DE!CPIPTICH: CCtfDENSATE DENIll.
FHASE SEPARATOR TAtX ELEVATIO*4
72G DESCRIPTI0ta: PADWASTE HOPPER C0t1PARTt1EHT ELEVATI0tl : 150 SS EQUIPr*EHT: 910ttE PCO*1 t?Jt:CER(S): 291 FIPE 20t1E:
72H DESCRIPTI0ti: SOLID RADWASTE DISPOSAL SYSTEN ELEVATI0tl : 165 SS EQUIPt1EtiT: itcttE R00:1 t!Ut1EER(SI: 378 FIRE ZONE:
72J DESCRIPTIOti: SOLID RADWASTE DISPOSAL SYSTEM ELEVATI0tl : 165 SS EQUIPt1EtIT: t10t4E PCOt1 flut:3Ept S1: 379
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SECTI0tt 2 - SAFE SHUT 00144 ANAL ROOM SUttt/tRT 06/25/3Z FEACH BOTTON ATONIC F0WER STATION L9 TITS 2 ADO 3 29 FIRE 20t!E:
77 DESCRIPTI0ti: UtIIT32 REACTOR RECIRC PUNP SET HVAC ELEVATI0tl : 165 SS EQUIPMEttT: NETHOD A ROON t!UMDER(SI: 375 FIRE ZCt!E:
78A Cott1ENTS: SEVERAL 4KV POWER FEEDS ARE ROUTED THROUGH THIS ZOt!E IN CCIOUITS. THE NETHOD "A" C0tOUITS IN THE ZONE WILL BE EHCAPSULATED.
THE GEllERAL AREA 0F THE TURBINE DUILDING TO DE ESTABLISHED DESCRIPTI0tt: TURBINE BLDG.
AS A NETHOD "B" ZOtIE. ROOM 262 ESTABLISHED AS NEW FIRE ZONE 147.
GEt4ERAL AREA ELEVATION : 91 SS EQUIPttEttT: NETH00 A,B ROCH hut 1BER(SI:
16,17,53,124*
FIRE ZCtlE 78AA DESCRIPT10tt: UNIT 22 STEAN PACKIttG EXHAUSTER ELEVATICH : 116 SS EQUIPMENT: tOtlE ROOM tlUNDER(SI: 116 FIRE ZOtlE:
78B CotstENTS: SEVERAL 4KV POWER FEEDS ARE ROUTED THROUGH THIS ZONE IN CatSUITS. THE NETH00 "A" C0tlDUITS IN THE ZOt4E WILL BE EHCAPSULATED.
DESCRIPTI0ti: TURBINE BLOG.
GEtiERAL AREA ELEVATI0tl : 116 SS EQUIPttENT: NETHOD A,B ROOM t!UNDERt SI:
126,185,186*
SECTIOtt 2 - SAFE SHUTDCh'N At4ALL_.J ROOM StW1ARY 06/25/82 FEACH ECTTOM ATCMIC F0WER STATIOtt L*1TTS 2 AL'O 3 30 FIPE 20t:E:
78E0 DESCRIPTIOti: Ut41T32 28 STEAt1 FACKIt4G EXilAUSTER ELEVATI0t4 : 116 SS EQUIFitEllT: Hot 4E PCN ti'MER(S B: 117 FIPE 2CtfE 78C DESCRIPTICt4: PAD. CHEM. LAC.
ELEVATIOtt : 116 SS EQUIFttEtiT: HOtlE RCCl nut 1CERIS): 127 FIPE ZCtlE:
7CCC DESC91PTI0ti: Ut1IT82 NECHANICAL VACUUtt FLtiP ELEVATI0tl : 116 SS EQUIFt1CNT: HottE FOCM nut 1BEPISI: 118 FIRE ZCt!E:
780 DESCRIPTIctt: COtNEHTI0t4AL CHEM.
LAB.
ELEVATICH : 116 SS EQUIFt1EtIT: ItOtlE F001 t1Ut1CERIS): 128
m SECTI0tl 2 - SAFE SHUTDOt:4 AttAL ROcti
SUMMARY
06/25/82 PEACH BOTTott ATOMIC Pot ER STATICN UITTS 2 A*C 3 31 FIRE ZOt!E:
7800 DESCRIPTICH: UNIT 83 3A STEAft FACKIt!S EXHAUSTER ELEVATI0tl : 116 SS EQUIPttEtiT: HollE R00ft HUMBERtS): 178 FIRE ZONE:
78E COMMENTS: SEVERAL 4KV POWER FEEDS ARE POUTED THROUGH THIS ZONE IN Cott0UITS. THE METHOD "A" Cot 00ITS IN THE ZONE WILL BE ENCAPSULATED.
DESCRIPTI0t4: COUNTING R00t1 GEt!ERAL AREA ELEVATICH : 116 SS EQUIPMEtiT: NETH00 A,B ROOM tlUMBER(S1: 134 FIRE 20tfE:
7CEE DESCRIPTICt4: Ut4IT83 38 STEAM PACKIllG EXHAUSTER ELEVATICH
- 116 SS EQUIPMEttT: t:0HE ROO*1 flUMBERIS): 177 FIRE 20t1E:
78F DESCRIPTION: UNIT 83 3A838 REACTOR FEED PUMP-TUFBIt3E LO ELEVATION : 135 SS EQUIPMENT: 940NE R00ftifUMBERIS): 275
SECTIOl 2 - SAFE SHUT 00tN AtlAL ROOM Stat 1ARY 06/25/02 PEACH BOTTOM ATONIC F0WER STATI0tl UtlITS 2 AHO 3 32 FIRE ZC'_IE:
78FF DESCRIPTI0tl: tPIIT33 MECHANICAL VACUUN PUMP ELEVATI0tl : 116 SS EQUIPMENT: tt0HE ROOM IU1 DER (S): 176 FIRE 2CtlE:
78G DESCRIPTI0ti: UNIT 32 2A82B REACTOR FEED PUNP TURDIllE LO ELEVATION : 135 SS EQUIPMEHT: ilOtlE ROCM PU1BER(SI: 232 FIRE 20tlE:
7cH CONNENTS: **-EXEMPTImi REQUESTED BASED ON t100IFICATIONS TO BE NADE TO PROVIDE ACCEPTABLE ISOLATION BETWEEN REDUtt0 ANT NETHODS OF SAFE SHUTOOWN EQUIPMEHT AHO CABLES. REFER TO TEXT.(SECTION 3)
DESCRIPTICH: CABLE SPREADING ROON ELEVATION : 150 SS EQUIPf1DIT: NETH00 A,B R00t1tu1 DER (S): 302 FIRE Z0tlE:
78J DESCRIPTION: UNITW2 2C REACTOR FEED PtkiP TURBINE LO ELEVATI0tl : 150 SS EQUIPMENT: H0HE POOM NUttDER(S): 303
~
f) f%.
b SECTICH 2 - SAFE SHUTDOWil AttALw,3 900M SUtittARY C6/E5/82 V
PEACH BOTT0!1 ATot1IC POWER STATION t##ITS 2 HF) 3 33 FIPE 20tlE:
78K DESCRIPTI0ft: UtIIT83 3C REACTOR FEED PUt!P TUPDINE LO ELEVATI0t1 : 150 SS EQUIPMEtIT* totif RCCN tu rc' " S:: 304 FIRE 20t:E:
7CL DESCRIPTI0ti: UtlIT83 3A REACTOR FEED PUMP TURCIt1E ELEVATI0tl : 165 SS EQUIrrittIT: H0tlE RC0!! IlUMBER( S l
- 463 FIRE 20t!E:
7CM DESCRIPTI0t4: UtlIT83 3B PEACTOR FEED PUt1P TURBIttE ELEVATI0tl : 165 SS EQUIPMEtlT: FlotlE i
R00t1 HUtFJER(S): 461 FIRE 20 tie:
70t1
~
DESCRIPTIott: UNIT 83 3C REACTOR FEED PUt1P 4
TURBIT!E ELEVATI0ft : 165 SS EQUIPt1Et4T: flotlE ROOM !!UMOERIS): 459
~
(~N
\\_)
./
SECTIG4 2 - S AFE SHUTDOWil AHAlk POO't Stat 1ARY 0$/25/60 PEACH BOTT0t1 AT0t11C P0t!EP STATICtl UttITS 2 At'D 3 34 FIPE ZONEa 76P DESCRIPTI0ti: UtlITC2 2C REACTOR FEED FU:P TUPBIt:E ELEVATI0t1 : 165 SS EQUIPttEHT: Hot!E R00t1 i Ut1CEA( S ): 421 FIRE 20ttE:
7PP DEECPIPTI0ti: Ut!IT#2 2B REACTOR FEED PUt1P TURBINE ELEVATION : 165 SS ECUIPttEtiT: tiottE R00t1 t!UttBER(S): 419 FIRE ZONE:
785 DESCRIPTICil: UNIT 82 2A REACTOR FEED PUttP TUP 0IttE ELEVATI0tl 165 SS EQUIrt1ENT: flot4E P00t1 IIUt1DERI S): 417 FIRE ZottE:
787 DESCRIPTICrt: Ut1ITR3 TURBItlE GENERATOR, TURBIT 1E BLOG. HVAC EQUIP.
ELEVATION : 165 SS EQUIPt1ENT: !!OtlE R00t1 t4UttBER(S): 465.466.467*
(o o
o
./
SECTI0tt 2 - SAFE SHUTDOWit AttAL's,,s POOrt SUtiMARY 06/25/82
\\ /
PEACH COTT0t1 AT0t11C POWER STATI0t4 tetITS 2 Atm 3 35 FIRE Z0 tie:
78U DESCRIPTI0ti: Ut31TR2 TUROIllE GEtiERATOR, TUPBIllE BLOG. HVAC EQUIP.
EEEVATI0tl : 165 SS EQUIPitEttT: t:0tlE P00t1 tu'CER(S): 433.434.435*
FIPE 20t!E:
78V DESCRIPTI0ti: UtlITW3 C0tOEt3SER ELEVATI0tl : 91 SS E7JIPt1EtlT: t1Ct1E P00t1 ItLitBERf S):
272,55.56*
FIRE 20tlE:
7E11 DESCPIPTI0ti: Ut4IT#2 C0t;0EllSER ELEVATION : 91 SS EQUIPt1Et4T flot1E P00t1 t!UttDER(S):
21,22,136*
FIRE 20t:E:
70X DESCRIPTI0ti: Ut4ITR2 C0f 0EtiSATE PUt1P ELEVATI0tl : 91 SS EQUIPt1EllT: flot1E R00t1 t Uff0ER(S): 20 l
--. - - -. ~.
SECTICil 2 - SAFE SHUTDOWH ANAL ROON SUtt1AM 06/05/8Z PEACH BOTT0t1 ATONIC POWER STATION tRIITS 2 WD 3 36 FIRE 20t:E:
78Y DESCRIPTI0ti: UNIT 83 C0tlDENSATE PUNP ELEVATI0tl : 91 SS EQUIPMENT: HOME R00t1 tU1BERt SI: S7 FIRE 20t1E:
79 C0tR1ENTS: THE "A" NETH00 C0tOUITS IN THE ZONE (ZA2B1249 ZC2B12491 TO BE EtlCAPSULATED TO ESTABLISH THIS ZOHE AS A NETH00 "B" ZONE.
DESCRIPTI0ti: Ut41T32 C0t0EllSATE BACVWASH RECEIVItfG TAl#(
ELEVATI0t1 : 91 SS EQUIrt1EHT: NETHOD A.B ROON tMIDERISI: 15 FIRE 20tlE:
40 CONNENTS: THE "A" NETHOD COHOUITS IN THE ZOHE (Z3B133. ZC38150.J173 TO BE EHCAPSULATED TO ESTABLISH THIS ZONE AS A -
NETHOD "B" Z0t:E.
DESCRIPTIOt4: LHIT83 C0tCENSATE BACKWASH MCEIVING TAHK ELEVATION : 91 SS EQUIrttENT: NETH00 A.B ROON t!LHDERIS): 50 FIRE Z0t1E:
81 DESC9IPTION: ELEVATOR NACHINE ROON s
ELEVATION : II6 SS EQUIPttENT: tt0HE ROOH tU1BER(S1: 431
i SECTICH 2 - SAFE SHUTDOWN AttAL ROOM Stat 1 ART 06/25/62 PEACH BOTTOM ATCt11C PCMER STATION tAJfTS 2 AHO 3 37
.I FIRE ZOHE:
82 CONMENTS: SEVERAL 4KV POWER FEEDS ARE ROUTED THROUGH THIS ZONE Ill C0tCUITS. THE NETHC0
A" Cot 0UITS Ita THE ZCt4E WILL BE EHCAPSULATED.
DESCRIPTI0ti: HEALTH PHYSICS l
UTILITY ROOM i
I ELEVATION : 116 SS EQUIPMFHT: METHOD A B ROCt1 11UNDER( S ): I29 FIRE ZOt4E:
83 I
DESCRIPTI0ti: TOILET i
l ELEVATION : 165 4
SS EQUIPriEffT HONE l
ROOM NUMBER (S): 415 4
j FIRE ZOME:
84 I
i f
DESCRIPTIOt4: JANITOR'S CLOSET I
ELEVATI0tl : 165 SS EQUIPMENT: HCHE ROOM HUMBER(S): 436 l
i FIRE ZOt1E:
85 1
i -
DESCRIPTION: UNITW2 PERSOHHEL l
ACCESS LOCK i
i i
ELEVATI0t1 : 165 j
SS EQUIPMENT: N0HE j
ROOM HUMBER:S): 406
,A
SECTION 2 - S AFE SHUTDOW4 ANALT ROON SUtttARY C6/25/02 PEACH EOTTON ATOMIC PCMER STATI0tl 1J4175 2 P O 3 38 i
t FIRE ZOtlE:
86 e
}
DESCRIPTIDH: (AIIT33 PERS0t#4EL ACCESS LOCK ELEVATI0tl : 165 SS EQUIPt1EllT: tole ROOM t1UtT>ERIS): 451 FIRE 20t4E:
87 DESCRIPTI0fl: LUDE OIL STORAGE ROON ELEVATI0t1 : 165 SS EQUIPHEt1T: PO4E ROOM t! UMBER (SI: 175 FIRE 20tlE:
88 DESCRIPTI0ti: UNIT 82 LUBE OIL STORAGE TAtlK ELEVATT0tt : 116 SS EQUIPMEtiT: tole ROON tU1BER(S1: 139 FIRE ZONE:
89 DESCRIPTI0t4: UNIT 53 LUBE OIL STORAGE TAtlK ELEVATI0tl : 116 SS EQUIPHEt1T: 110HE R00t1 t4 UMBER (S): 179 1
SECTIG4 2 - SAFE SHUT 00Wil At1ALY R00t1 SUt1 MARY C6/25/82 PEACH BOTTOM ATOMIC POWER STATI0tl LPIITS 2 #to 3 39 FIRE Z0tlE:
90 DESCRIPTI0ti: UtlIT82 TG LUDE OIL RESE1VOIRS 8 EQUIP ELEVATI0t1 : 135 SS EQUIPt1EllT: tele RCOt1 tlUttCER(5): 230 FIRE Z0 tie:
91 DESCRIPTICtt: UtlITR2 TG EtfERG.
BEARIt4G OIL PUt1P DATTERY ELEVATI0tl
- 135 SS EQUIPitEtli: tele R00t1 tlUMDERtS1: 224 FIRE ZOtlE:
92 DESCRIPTI0ti: UtlIT32 tt0 TOR C0t4 TROL CEt4TER ELEVATI0tl ' 135 SS EQUIPfiEt4T: tele POOM tlUt10ER(S): tOJE FIRE 20t4E:
93 DESCRIPTI0ti: UtlIT33 TG LUBE OIL RESERVOIR $ EQUIP.
ELEVATI0tl : 135 SS EQUIPttEt4T: t10tlE R00*1 flutt3ER(S): 273 w
SECTIcti 2 - SAFE SHUTDOWN ANAL ROOM
SUMMARY
06/25/82
)
FEACH EOTTON ATCMIC FO'4ER STATION L"!TTS 2 MO 3 40 FIRE ZOtlE:
9 'e OESCRIPT10ti: UtlITt3 TG EMEPG.
CEARIt:G OIL FUMP BATTERY ELEVATI0tl : 135 SS EQUIrttEtIT: HONE R00t1 t1 UMBER (SI: 276 FIRE ZONE:
95 DESCRIPTI0ts: UtlIT83 MOTOR CCt1 TROL CENTER ELEVATIOtt : 135 SS EQUIrttEtlT: tot!E R0011 t! UMBER (S1: tCt!E FIRE ZollE:
96 DESCRIPTI0ti: UNITS 3 3A FEEDWATER HEATER ELEVATI0t1 : 135 SS EQUIPt1EffT: Not1E FCott t!Uf1 DER (S1: 271 FIRE ZCt:E:
97 DESCRIPTI0ti: UtlITR3 ?B FEEDWATER HEATER ELEVATI0tl : 135 SS EQUIPMEtif: t10t1E F00t1 t!UttDERIS): 270
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SECTICH 2 _ SAFE SHUTDOWN AttALT ROCH SUMitARY 06/25/82 FEACH BOTTON ATONIC F0WER STATION t.91TTS 2 mfd 3 42 FIRE 20tEt 102 l
DESCRIPTI0ti: UPIIT32 2A FEEDWATER HEATER ELEVATION : 165 l
SS [GUIrttENT: PO4E j
ROCH tlUMDER(S): 411 i
FIRE 20tlE: 103 4
i' DESCRIPTI0ti: tA4ITC2 EB FEEDWATER HEATER i
ELEVATI0tl : 165 i
l SS EQUIPMEt4T: PO4E i
i R00ft nut 1BER(SI: 412
]
FIRE ZCflE: 104 DESCRIPTION: UNIT 32 2C FEEDWATER HEATER i
ELEVATI0tl : 165 l
ROON HUttDER(SI: 413 FIRE Z0tlE: 105 i
DESCRIPTI0t4: UNITR3 3A FEEDWATER HEATER I
4 ELEVATICH : 165 4
SS EQUIrttENT: H0tlE 4
i ROOM IfUt' DERF SI: 456 1
2
-..--,-.._--.-.m...,
SECTION 2 - SAFE $4UTDOWN ANAL 1 R00tt StRtMARY 06/25/82 PEACH BOTTON ATOMIC F0WER STATICH
(#4ITS 2 H C 3 43 4
FIRE ZCttE: 106 y
DE0CRIPTIcti: Ut4IT83 3B FEE 0 WATER HEATER ELEVATI0t1 : 165 SS EQUIrttEffT: t!Ot!E ROOM FAR1BER(S): 455 FIRE 20 tie: 107 DESCRIPTION: Ut1IT83 3C-FEEDWATER HEATER ELEVATI0H : 165 SS EQUIrt1ENT: fl0HE R00t1 tPJMBER(S): 454 FIRE ZotiEs 103 COMMENTS:
FIRE ZONE: 109 DESCRIPTIOH: UNITS 3 TURBINE BLOG H&V FREFILTERS &
HEPAFILTERS ELEVATICH : 195 SS EQUIPMENT: HONE POOM HUttBERfS): 527.528
('.
SECTION 2 - SAFE SHUT 00WH A!1ALw,.a ROOM Sutt1ARY 06/25/82 yr FEACH EOTTOM ATCMIC FCMER STATI0tl LHTTS 2 A'O 3 44 FIRE ZOffE: 110 DESCRIPTI0f t: Ut4IT82 TURBIllE BLDG H1V FREFILTERS S HEPA FILTERS ELEVATI0'i : 195 SS EQUIPMEt;T: H0tlE RCOM intBER(S): 513 FIRE ZCftE: 111 DESCRIPTIOft: STAIRWAYS 5 ELEVATI0tt : 116 SS EQUIrt1EtiT: flottE R00t1 tu1BERIS):
FIRE 20ttE: 112 DESCRIPTI0ti: STAIRWAY 31 ELEVATI0ff : 116 SS EQUIP!1EtiT: tiot!E ROOH tuiBERISI:
FIRE ZOt!E: 113 DESCRIPTI0tt: STAIRWAYR3 ELEVATI0tl : 116 SS EQUIPMEllT: tiottE ROOM IU1CER(S):
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SECTICN 2 - SAFE SHUT 00Mit AftAL ROOM SUtttARY 06/25/82 PEACH BOTTOM ATOMIC POWER STATI0ti tRIITS 2 StC 3 46 FIRE ZOtE: 118 COMMENTS: THE "B" METHOD CABLES Iti THE ZOttE t ZB301802A.Bl TO BE REROUTED OR EHCAPSULATED TO ESTABLISH THIS ZOttE AS A NETHCO "A" 20ttE.
DESCRIPTI0ti: UtlIT23 3A/C EMERG.
i BATTERY ELEVAT10H : 135 SS EQUIPHEHT: NETHOD A,B ROOtt HUMBER(Sl: 266 FIRE 20t1E: 119 COMMENTS: THE SEVEN NETH00 "D" CotCUITS IN THE ZONE TO BE REROUTED CR EHCAPSULATED TO ESTABLISH THIS ZONE AS A NETH00 "A" 20tlE.
DESCRIPTION:.Ut!IT23 4KV EMERG.
]
SMGR. 30A17 ELEVATI0tl : 136 i
SS EQUIPMEt3T: NETHOD A.B POct1 trut1DERtS): 261 FIRE ZCt4E: 120 Cott1ENTS: THE "B" NETH00 EQUIPNENT (DATTERY CHARGER) AFC CABLES (ZB381114A, ZD30001El IN THE 20ttE TO BE RELOCATED AtlD/OR Et;CAPSULATED TO ESTABLISH THIS ZONE AS A METHOD "A" ZOttE.
DESCRIPTICH: UNIT 83 4KV EMERG.
SMGR. 30A15 ELEVATION : 135 f
SS EQUIPMENT: NETH00 A.B R00f1 HUMBER(S): 267 4
j FIRE ZONE: 121 C0ft1ENTS: THE "A" NETHOD CABLES IN THE ZONE (ZC341702J 0G05H)
TO BE REROUTED OR EHCAPSULATED TO ESTABLISH THIS ZOHE AS A HETHOD."B" 20t3E.
=
DESCRIPTIDH: tR41Tf*3 4KV ENERG.
SMGR. 30A18 ELEVATION
- 135 SS EQUIPMEt3T: NETHOD A,B P00'1 1: UMBER t S ): 265 i
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SECTICH 2 - SAFE SHUTDOWH AtlAL)
ROOM SUttMARY 06/25/82 FEACH BOTT0t1 ATOMIC F0WER STATION UNITS 2 AHr) 3 48 FIRE 20ME: 126 Cott1ENTS: THE "B" METN00 EQUIFt'ENT IBATTERY CHARGERI AND CABLES Iti THE ZONE (ZB2ED01E. ZD20D01E, ZB2B6143Z. ZB2B1122Al TO BE RELOCATED Atc/OR EttCAPSULATED TO ESTABLISti THIS ZONE AS A DESCRIPTICH: UNIT 32 AKV EMERG.
METHOD "A" ZONE.
SWOR. 20A15 ELEVATI0H : 135 SS EQUIrt*ENT: NETHOD A.B R00*1 t!UttBERtS): 227 FIRE ZOtiE: 127 C0titEl.TS: THE "A" NETHOD CABLES IN THE ZOHE (ZA2B1021A. ZA2B1022A ZA2A1505Al TO BE RERCUTED OR ENCAPSULATED TO ESTABLISH THIS AS A t1ETHOD "B" ZONE.
DESCRIPTICH: LHIT82 28/D EMERG.
BATTERY ELEVATI0H : 135 SS EQUIFt1ENT: NETHOD A.B ROON tutBERES): 225 FIRE ZCttE: 123 CCtt1EHTS: THE "B" NETHC0 CABLES IN THE ZONE (ZB201C02A.Bl TO BE REROUTED OR EHCAPSULATED TO ESTABLISH THIS ZONE AS A NETHC0 "A" ZONE.
DESCRIPTICH: Ut4IT32 2A/C ENERG.
BATTERY ELEVATI0H : 135 SS EQUIPMENT: METHOD A.B ROOM HUMSERISI: 218 FIRE ZONE: 129 DESCRIFTI0tt: PLANT CortPUTER ELEVATION : 150 SS EQUIrttENT:.H0HE ROOM t:UMDERISla 301
SECTIOtt 2 - SAFE SHUTDOWN ANAL WOON
SUMMARY
06/25/82 PEACH BOTTOM ATCMIC POWEd STATION LPIITS 2 Ato 3 49 FIRE ZONE: 130 COMMDITS: THE "A" HETHOD COtiDUITS IN THE ZONE (ZA2B1249. ZA2B143.
ZC2B1247) TO BE Et1CAPSULATED TO ESTABLISH THE ZONE AS A NETH00 "B" 20t4E.
DESCRIPTI0ft: PIPE tut #1EL ELEVATI0t1 : 91 SS ECUIPtfEllT:-METHOD A.B ROOM tFJMBER(SI: 18 FIRE 20tlE: 131 DESCRIPTION: PIPE tut #1EL ELEVATION : 91 SS EQUIPMEtIT: METHOD A ROOM HUMBER(S): 19 FIRE ZONE: 132 COMMENTS: THERE ARE THREE CABLE SCHEMES IN THIS ZONE (2A1603.
2A1706. 3A1809) THAT HAVE TO BE REDESIGt!ED TO PROVIDE ELECTRICAL ISOLATI0tl. THEY WILL THEN bE DCAPSULATED AS DESCRIPTI0tt: D ENERG. DIESEL REQUIRED TO ESTABLISH THIS ZOt1E AS A METHOD "B" ZOt3E.
GEttERATOR & SUPPORT EQUIP.
ELEVATION : 000 SS EQUIPt1EtiT: NETHOD A.B POOM tRRtBER(S): Hot 1E FIRE ZONE: 133 COMMENTS: THERE ARE THREE CABLE SCHEMES IN THIS ZONE (2A1603.
2A1706. 3A1809) THAT HAVE TO BE REDESIGNED TO PROVIDE ELECTRICAL ISOLATION. THET WILL THEN BE ElaCAPSULATED AS l
DESCRIPTION: C ENERG. DIESEL REQUIRED TO ESTABLISH THIS ZONE AS A NETHOD "A" ZONE.
GEtlERATOR A SUPPORT EQUIP.
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SECTI0tl 2 - SAFE SHUTDOL&4 AHAL)
ROOM
SUMMARY
06/25/62 PEACH EOTTOM ATOMIC F0WER STATION tf1TTS 2 AFD 3 52 FIPE 20'iE: 142 DESCRIPTIO!I: UttIT82 2A.2DS 2C WATER FtA1P ELEVATI0H : 000 SS EQUIFMEtIT: IDIE ROOfftu BERIS): t03E FIRC ZOHE: 143 CotttENTS:
um. EXEMPTION REQUESTED TO EITHER LOSS OF OFFSITE POWER OR MANUAL OPERATICils TO EFFECT HOT SHUTDoutt REQUIRENENTS. REFER TO TEXT.(SECTI0t1 31 DESCRIPTION: UNIT 83 3A.3B.
3Ct3D HPSt4 PUMPS ELEVATION
- 000 SS EQUIPMEtiT: t1ETHOD A.B ROON HUMBERtS): FO1E FIRE ZONE: 144 C0tttENTS:
- -EXENPTION REQUESTED TO EITHER LOSS OF OFFSITE POWER CR MAtlUAL OPERATIONS TO EFFECT HOT SHUTDOWN REQUIREMENTS. REFER TO TEXT.(SECTION 3)
DESCRIPTI0tt: UNIT 82 2A.28, 2C12D HPSW PUMPS ELEVATI0tl : 000 SS EQUIPttEtiT: NETHOD A.B POOM tu1BERIS): HollE FIRE 20t!E: 145 DESCRIPTI0ti: DIESEL DRIVEN FIRE FUMP TRAVELING SCREENS ELEVATI0t1 : 000 SS EQUIPMEHT: tale ROON NUMBER (S): ID3E
)
SECTICtl 2 - SAFE SHUTDOM4 AllAL ROOM
SUMMARY
06/25/02 PEACH COTTOM ATOMIC POWER STATICil LR4TTS 2 Ato 3 53 FIRE ZCt!E: 146 DESCRIPTICt4: DIESEL GEPIEPATCR CO2 STORAGE TAttK 5TH BAY 4
ELEVATICtl : 000 SS EQUIPMENT: itCt!E ROOM t! UMBER (SI: H0t4E FIRE ZOtlE: 147 COMP'5N1 S: HALF OF THE SAFE SHUTDOM4 PACENAYS IN THE AREA WILL BE E!!CAPSULATED TO PROVIDE THE I4ECESSARY ISOLATICtt.
DESCRIPTIOti: TURBIT 4E BLDG.
CORRIDOR ELEVATICtl - 135 SS EQUIPMENT: METHOD A,B PCOM HUMDER(S): 262
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4 Supplemental Information l
and Exemption Requesta
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r-Section 3 O
Text (Supplemental Information and Exemption Requests)
This section is divided into four parts.
The first part contains the discussion of the four fire zones that utilize a method other than Method A or B to achieve hot and cold shutdown.
The second part contains the exemption requests. The third part contains a discussion on instrumentation required for operator information. The fourth part discusses the emergency lighting in those areas needed for operation of safe shutdown equipment and in access and egress routes thereto.
Part 1 - Third Method of Shutdown Fire Areas 21 and 29 - These fire zones house the Main Steam lines, the outboard Main Steam Isolation Valves and a few valves for the RCIC (Method A) and HPCI (Method B) systems.
For a fire in these areas, a different method of safe shutdown can be used to achieve hot and cold shutdown. For this method, the reactor is depressurized by manually controlling the Main steam relief valves in the depressurizatior.
mode. The opening of these valves allows reactor steam to be discharged to the torus.
Make up water to the reactor vessel is supplied by a Core Spray pump taking suction from the torus.
Heat is removed from the torus by one f~)
loop of the RHR system operating in the suppression pool cooling mode. Torus water is circulated through an RHR heat exchanger and returned to the torus.
Heat is removed from the RHR heat exchanger by the HPSW system which in turn dissipates heat to the river.
The reactor can then be depressurized below 75 psig by additional operation of the relief valves. When the reactor has been depressurized below 75 psig, the RHR system can be transferred from torus cooling to the shutdown cooling mode.
In the shutdown cooling mode, heat is removed from the RHR heat exchanger by the HPSW system, which in turn dissipates heat to the river.
The shutdown cooling mode of RHR will maintain the reactor-in a cold shutdown condition.
l There is no equipment or cabling associated with this method of shutdown located within these main steam line tunnels, therefore, this method of achieving both hot and cold shutdown would be available following a fire in these zones.
Fire Areas 61 and 64 - These rooms contain the instrument racks for both the HPCI and RCIC systems.
These racks are required for system operation; the j
loss of both of these racks could disable both HPCI and RCIC systems.
The different method of hot and cold shutdown discussed in the respense to fire zones 21 and 29 above also bypasses these zones. Therefore, following a fire in these zones, the above method would be available to obtain both hot and cold shutdown.
V 3-1 c
p Part 2 - Exemption Pequests
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The following fire zones do not presently meet the requirements of Section III G.2 of Appendix R:
Fire Zone SC - Unit 2 Torus Compartment Fire Zone 13C - Unit 3 Torus Compartment Fire Zone 5H - Unit 2 Reactor Building, 135', General Area Fire Zone 13H - Unit 3 Reactor Building, 135', General Area Fire Zone SJ - Unit 2 Reactor Building, 165', General Area Fire Zone 13J - Unit 3 Reactor Building, 165', General Area Fire Zone 72A - Common Remote shutdown panel area Fire Zone 78H - Common Cable Spreading room Fire Zone 108 - Common Control room Fire Zone 143 - Unit 3 High Pressure Service Water pump bay Fire Zone 144 - Unit 2 High Pressure Service Water pump bay We are not proposing alternative shutdown capabilities for these fire zones. The following discussions will provide the design features of these areas and justification for the exemption requests.
Accordingly, Philadelphia Electric Company hereby requests an exemption pursuant to 50.48 (c) (6) regarding regulation 10CFR50, Appendix R,
Section III.G.2 as described below.
The following discussions on the individual fire zones will describe the existing installation, the difficulty in meeting the requirements of Section
(-)
III G.2, and the modifications that are being proposed to provide reasonable assurance that a fire in the area would not involve equipment and cables for the redundant safe shutdown methods.
We have held discussions with a consultant with expertise in the area of fire protection. We plan to engage this consultant to evaluate the adequacy of our proposed modifications.
If our proposed modifications are not sufficient, we will implement additional improvements based on their recommendations to assure that both methods of safe shutdown equipment will not be involved in the fire.
Our proposed modifications may also be changed as a result of their review.
The consultant will also review the need for coating structural steel as required.
Fire Zones SC and 13C - Torus compartments. There are several valves within this zone for both methods of shutdown.
The majority of the valves are normally in their correct operating position and there are no conceivable fire induced failures in the valve or its cables that could cause it to move from this position.
The valves that are require " to be functional are physically located 135*
apart on the torus with no intervening combustibles between ther..
An alternative method of safe shutdown cannot be used in these fire zones since the torus is instrumental in providing a mechanism for decay heat removal.
There is no other installed equipment that could provide the necessary heat sink.
()
We request an exemption on the need for an automatic suppression system in this area based on the extensive physical separation between the redundant 3-2
r safe shutdown equipment (135'-more than 90 feet), the low installed O
combustible loading (less than 200 BTU /sq. ft.), the lack of intervening combustibles and the existance of smoke detectors in the area.
In order to meet the requirements of III.G.2, the valves and cables would have to be encapsulated within 3 hr. rated fire enclosures or an automatic suppression system would have to be added to the area. Neither of these two modifications would provide any additional improvements to the existing installation based on the physical arrangement of the fire zones.
Fire Zones SH and 13H - General area, 135' elev., Reactor buildings. These general areas are shown on the attached physical layout drawings (Figure 1).
In both zones, the half of the zone North of the reactor centerline houses cables and equipment required for operation of Method B and the half of the zone South of the reactor centerline houses cables and equipment required for operation of Method A.
There are a few cables within these zones that belong to the opposite safe shutdown method; these cables will be encapsulated within three hour rated fire barriers and do not need to be considered as part of the remaining discussion.
Several RHR valves are located within the isolation valve rooms on this elevation.
The power and control cables for these valves must be routed through this area.
Additionally, there is other equipment on these elevations that would either be difficult or impossible to relocate to other fire zones. Alternative shutdown methodology is also impossible since the RHR system valves are essential in establishing torus and shutdown cooling.
It
(}
would be difficult to separate the zone into two distinct fire zones without severely restricting operations.
We propose the installation of an automatic suppression system (water) in the West corridors. This system would be so designed as to prevent a fire from traveling this corridor. The intervening combustibles in this corridor (open cable trays) will be coated with a flame retardant material along the length of the corridor to eliminate a combustible pathway.
The East corridors contain no fixed combustible loading nor equipment I
required for either method of safe shutdown.
l We, therefore, request an exemption to the requirement for three hour rated fire barriers between redundant shutdown equipment based on the establishment i
of a water curtain and the application of flame retardant material in the
[
West corridors. and the physical separation (at least 40 feet of free space with no combustible loading) in the East corridor. The fire zone is already equipped with an automatic detection system.
Fire Zones 5J and 13J - General area, 165' elev., Reactor buildings.
The major dif ficulty in these fire zones are the Emergency Load Centers.
All l
four of the Emergency Load Centers per Unit are located on this elevation.
l The redundant load centers in each Unit are separated from each other by twelve foot high block walls.
The load centers feed the motor control centers that feed valves for the safe shutdown equipment.
()
An alternative method of safe shutdown cannot be used in these fire zones j
since all of the plant on site ac power (480V and lower) is routed through 3-3
("%
the load centers located on this elevation.
There is not enough room
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available in any Class 1 structure in the plant in order to relocate two of these transformers and load centers.
We propose to dedicate these elevations to one method of safe shutdown equipment by encapsulating the cables and equipment of the other methods' cables, with the exception of the load centers, within three hour rated fire barriers. All of the fixed combustibles within the vicinity of the redundant load centers will be removed or coated with a flame retardant material and the areas around the redundant load centers will be provided with curbs to prevent the transport of fire across the floor.
This will assure that the redundant load centers will not both become involved in the same fire. The block walls establish a barrier between the redundant load centers such that there is the equivalent of twenty feet of free space between the load centers.
Smoke detectors are already installed within the fire zone including in the vicinity of the load centers.
We, therefore, request an exemption to the need for an automatic suppression system in the area based on the implementation of the above modifications, the existing barriers between the load centers, and the low combustible loadings (.35 hour4.050926e-4 days <br />0.00972 hours <br />5.787037e-5 weeks <br />1.33175e-5 months <br /> rating required) in the fire zone.
Fire Zone 72A - Radwaste building, several elevations.
The only room of concern in this fire zone is an elevation 165' in the vicinity of the remote shutdown panels (room 381).
This area contains the remote shutdown panels and the HVAC equipment for the battery rooms, switchgear roems and the main
()
control room for both Units.
The combustible loading in this room is entirely electrical cable and is less than 40,000 BTU /sq. ft. (half-hour rating).
The cables and equipment in the remainder of the rooms within fire zone 72A will be rerouted or encapsulated to bring them into full compliance with the requirements of Section III.G.2.
l We have identified the physical location of the cables and equipment required for both methods of safe shutdown within this area.
We will install the necessary fire rated barriers in this area to provide assurance that both methods of safe shutdown equipment will not be damaged by a fire in the area.
Smoke detectors are already installed in the vicinity of the remote shutdown panels.
Fire Zone 78H - Cable Spreading room.
There are many raceways for both methods of safe shutdown located within this fire zone. The cables required for cafe shutdown located within this zone have been identified and those cables that actually share raceways with redundant safe shutdown cables will be rerouted into the appropriate raceways. The physical arrangement of the raceways will be examined by our consultants on fire protection.
We will install the necessary barriers, shielding, and encapsulations at their recommendation to provide assurance that both methods of safe shutdown equipment will not be affected by the anticipated fires in this area. This area is currently protected by an automatic detection and suppression system.
O
(_/
Fire Area 108 - Control room.
This area contains the controls for both methods of safe shutdown. The RCIC system can be controlled from the remote 3-4
T rT shutdown panels, however, controls for other components of Method A are
(,)
located within this room.
There are no redundant safe shutdown controls located within the same panels in this zone.
This fire zone is continuously occupied as specified by the Licensee's Technical Specifications. The combustible loading within this zone in low (10,000 BTU /sq. ft.) and is essentially entirely of an electrical nature. Smoke detectors are already installed within the area.
Fire Areas 143 and 144 - HPSW Pump bays.
As shown on the attached architectural drawings A-173, all four of the HPSW pumps per unit are located within a common fire zone in the pump structure. The HPSW pumps are required for torus cooling during the period of hot shutdown and for shutdown cooling for the period of cold shutdown.
We request an exemption to the requirement to assume a less of offsite power coincident with a fire in one of these fire areas or an exemption to allow a manual operation of mechanical equipment in a remote building in order to support achieving hot shutdown.
If a loss of offsite power is not assumed, the Units can be safely shutdown utilizing conventional plant equipment that is not contained within this fire area.
There are no power or control cables within this fire zone for any of the offsite power supplies. A fire in this area would not cause the loss of either the generating Unit or offsite power.
The circuit breakers for the equipment within this area have been demonstrated to be properly coordinated
(~D up through the offsite source circuits such that the load breakers will
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operate prior to the corresponding source breakers.
If a manual operation outside the control room is assumed the use of HPSW from the other unit can still be established following a loss of the pumps in one room by opening the manual cross tie valves, one located in each of these areas.
This manual operation could be performed within the time frame of HPSW for torus cooling (about one hour) and definitely within the time frame for shutdown cooling.
The combustible loading within the fire area is very low (less than 1500 BTU /sq. ft.) and smoke detectors are already installed within the area.
Part 3 - Instrumentation In the letter dated 6/3/81 from J.
W.
Gallagher to D.
G.
Eisenhut, we committed to providing six process parameters to the control room operator as part of the Safe Shutdown Analysis.
Since the parameters that were identified (Reactor temperature, pressure, and level, containment pressure, and torus level and temperature) had never been categorized as Class lE devices, their cables and power feeds were never controlled. This being the case, the cables were never assigned safeguard routings and were not routed with any inherent separation.
These instruments were not included in the Safe Shutdown Analysis since it was apparent that they would have to be ultimately rerouted anyway.
AV 3-5
F
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f~y The cables and feeds for the above listed parameters will be rerouted
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subject to the following criteria.
1)
One set of the above parameters will be assigned to Method A.
2)
One set of the above parameters will be assigned to Method B.
3)
The power supplies and cables for the Method B parameters will be routed within Method B fire zones or will be encapsulated in a rated fire barrier when routed within a Method A fire zone.
4)
The Method B parameters will readout in the main control room.
5)
The power supplies and cables for the Method A parameters will be routed within Method A fire zones or will be encapsulated in a rated fire barrier when routed within a Method B fire zone.
6)
The Method A parameters will readout on the remote shutdown panel and in the main control room.
The transfer switch at the remote shutdown panel will bypass and divide any fire induced failures in the control room on the Method A parameters.
Following completion of these modifications the instrumentation will be in full compliance with the 6/3/82 commitment.
Part 4 - Emergency Lighting
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As discussed previously, operations for purposes of safe shutdown are performed either in the Main Control Room or at the Remote Shutdown Panels.
It may also be necessary to access the cable Spreading Room, the Emergency Switchgear Rooms, the fifth room in the Diesel Generator Building, and the IIPSW pump bays.
These areas are supplied by the Emergency AC (power derived from the diesel generators) Lighting system; the illumination levels are 20 foot candles in the Main Control Room and 10 foot candles in the other areas.
Portions of the Emergency Lighting Systems described above may be disabled by a fire in some fire zones. Therefore, the Emergency Lighting in the areas needed for operation of safe shutdown equipment required to achieve hot shutdown and in access and egress routes thereto will be upgraded by a lighting system with at least an eight hour battery power supply, i
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SECTION h i
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High-Low Pressure Interface Analysis i
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Section 4 High-Low Pressure Interface 3
The results of the High-Low Pressure Interface analysis as submitted in the letter from J. W. Gallagher to D. G. Eisenhut dated June 3, 1981 and the completion of the study are presented below.
The Requests for-Additional Information are repeated from Enclosure 2 of the letter from M.
B. Fairtile to E. C. Bauer, Jr. dated May 5,1982.
RAI.2.a.
Identify each high-low. pressure : interface that uses redundant electrically.. controlled devices (such as two series motor operated a/alves) to isolate or preclude rupture of any primary coolant boundary.
Response
There are nine high-low pressure interfaces per unit at Peach Bottom.
Of these, only"two per unit use redundant electrically operated devices-(two series motor operated valves in each case) to isolate or preclude rupture of the primary coolant boundary.
These two lines are the RHR shutdown cooling suction line (valves MO-10-17, 18) and the Mut head spray line (valves MO-10-32,33).
RAI.2.b.
For each set of redundant valves identified in a., verify the redundant cabling (power and control) have adequate physical
()
separation as required by Section III.G.2 of Appendix R.
Response
The MO-10-17 and MO-10-33 valves are 250V DC motor operated valves and the MO-10-18 and MO-10-32 valves are 39 480V AC motor operated valves.
In order for the DC valves to open as a result of a power cable failure, would require a +125V DC hot short on two specific conductors, two other conductors shorting to each other and the fifth wire hot shorting-to negative 125V DC.
These cables are each routed in their own conduits with one other control cable in each conduit. This control cable provides valve position indication and control. There are no combination of failures to the control cable that could cause the valve to operate. Additionally, there is no negative 125V DC in this control cable.
Therefore, it is highly improbable for the power cable to develop the necessary five correct shorts in order to open spuriously.
Similarly, between each 480V AC valve and its motor control center there is a power and control cable.
Again, the. control cable contains valve position indication and controls there are no combinations of failures to this cable that could cause the valve to open.
In order for the power cable to cause the valve to go open, a three phase to three phase correct rotation hot short would have to occur on the power cable.
The power cables are multi-conductor cables, so the likelihood of all three phases receiving a different hot short are remote.
There are several control cables for each valve between its motor control center and the control room whose failure could cause misoperation.
4-1
~
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- e The control cables for the shutdown cooling valves are routed from the Og control room to the remote shutdown panels from the remote shutdown panels to the motor control centers and logic panels in the cable spreading room. The control cables for the head spray valves are routed from the control room to the cable spreading room to the motor control centers.
The circuit breaker for one of the head spray valves is being administratively controlled by locking it in the open position when the system is not required to be in operation.
Since the power is removed from the valve and the discuscicn in the response to RAI.2.b. above showed that the failure of the cables between the valves and the motor control center that caused the valves to open is considered incredible, this blocking will provide assurance that these valves will not open spuriously.
RAI.2.c.
For each case where adequate separation is not provided, show that fire induced failures ' hot short, open circuits or short to ground) of the cables will not cause maloperation and result in a LOCA.
The fire zones or areas that contain cables for the shutdown cooling valves are as follows:
I MO 2-10-17 MO 2-10-18 Control room Control room Cable spreading room Cable spreadit g room Femote shutdown area Pemote shutdown area l
(
M-G set room 165' elev. reactor bldg.
135' elev. reactor bldg.
MO 3-10-17 MO 3-10-18 Control room Control room Cable spreading room Cable spreading room t
l Remote shutdown area Remote shutdown area 135' elev. reactor bldg.
M-G set room j
l 165' elev. reactor bldg.
RBCW pump room Fire induced failures in the conmon areas above could cause misoperation of these valves. The cables and controls for one shutdown cooling valve per unit will be modified to preclude this misoperation. The modifications will include encapsulation of cables with appropriate fire barriers in common areas, and possibly the installation of bypass switches on the valve controls. Refer to the discussion for fire zones 72A and 108 in Section 3 of the report for the exemption requests at the remote shutdown panel and l
control room respectively.
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4-2
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SECTICN 5 Associated Circuits Analye'.s O
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Associated Circuits Analysis As stated in the letter from J. W.
Gallagher to D.
G.
Eisenhut, dated June 3, 1981, we have analyzed all associated circuits in the following manner:
(1)
All the power sources required for safe shutdown were identified.
The non-safe shutdown loads connected to these sources were analyzed to verify that their isolating devices with minor modifications, (circuit breakers and fures) are properly coordinated to insure isolation at the power source without affecting the feed to the power source.
(2) All circuits that are connected to circuits required for safe shutdown were either included in the Safe Shutdown Analysis or were analyzed to ensure that they were properly isolated from the safe shutdown circuits.
This analysis did demonstrate that some additional fusing is required.
All circuits for equipment whose spurious operation would adversely affect safe shutdown were included in the safe shutdown analysis.
(3)
Associated circuits that share raceways with safe shutdown circuits were analyzed to show that their failure due to a fire in a fire area will not cause adverse effects to the safe shutdown circuits
( })
with which they share raceways in other fire areas. The basis for this analysis was the results of the Sandia Labs cable fire tests where it was demonstrated that a sustaining fire could not be established due to an electrical fault in an IEEE 383 qualified cable. A fire in a fire area will be restricted to cables in that area and the only effects remote to the fire area might be fault current in the cables.
As demonstrated by the Sandia Lab tests, fault currents will not start a sustaining fire in an area remote to the fire area.
Our method of analysis as described in Item (1) above differs from the two approaches outlined in the letter from M.
B.
Fairtile to E.
G.
- Bauer, l
Jr., dated 5/4/82, however the analysis was complete prior to the receipt of the above letter and our method does demonstrate that associated circuits l
involved in a fire, as modified in accordance with the proposals identified in the balance of this section, will have no effect on the safe shutdown circuits and thus we believe it meets the intent of your request.
Rather l
than list every associated circuit in every fire area and analyze their effects on safe shutdown, we have demonstrated that the associated circuits l
will have no adverse affect on the safe shutdown circuits.
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l 5-1
D.C.
System The de power sources required for safe shutdown are the four 125 volt dc batteries (AD01, BD01, CD01, and DD01)which feed the following buses required for safe shutdown (See figure 1):
D07 D21 AD13 AD18 D08 D22 ED13 BD18 Dll D23 CD13 D12 D24 DD13 The types of fuses used to feed these buses and loads on these buses are Pussmann type fusetron, Chase Shawmut form 480 class L, and Chase Shawmut class K-5.
We have performed a study which demonstrated through the time-current characteristic curves that the fuses are properly coordinated such that for any fault induced by a fire the fuse protecting the faulted equipment would isolate the fault before any other fuse closer to the batteries. For every bus we have demonstrated that the load fuse with the highest reting would isolate the fault before the bus feeder fuse and thus any load fuse with a lower rating would isolate the fault before the bus feeder fuse.
The maximum fault current for the batteries is approximately 12600 amps and all of the fuses are properly coordinated for currents below this value.
The battery chargers are current limiting devices with a maximum output of 240 amps.
O A.C.
System The ac power sources required for safe shutdown are the four diesel generators (OAG12, OBG12, OCG12, ODG12) which feed the following buses required for safe shutdown (See figure 2):
1) 4 kV buses A15, A16, A17, and A18.
2) 480 volt load centers B10, Bil, B12, and B13.
3) 480 volt motor control centers:
B27 B36 B49 BS5 B61 B28 B37 B50 B56 B62 B32 B38 B53 B59 B84 B35 B39 B54 B60 4) 120 volt buses YO3, Y33, Y34, and Y35.
The 4 kV breakers are tripped by General Electric type IAC relays. The 480 volt load center breakers are ITE type K600 and K1600, the 480 volt motor control center breakers are Westinghouse type HFA, HFB, HKA, and Tripac, the 120 volt breakers are Westinghouse type EB.
We have performed a study which demonstrated through the time-current s,)
characteristics curves that with some minor modifications the breakers will l
be properly coordinated such that for any fault induced by a fire the breaker I
5-2
~
4 protecting the faulted equipment would trip before any other breaker closer C]-
to the diesel generator.
For every bus we have demonstrated that the load breaker with the highest rating would trip before the bus feeder breaker and thus any parallel load breaker with a lower rating would also trip before the bus feeder breaker.
Exceptions to Coordination Since some 480 volt loads are in the same fire area as the motor control center that feeds them and a fire in this area could disable the motor control center, it is not necessary for these load breakers to coordinate with the motor control center feeder breaker.
For a high resistance fault on a 4 kV load circuit with a ground fault current from 5 to 17 amps, the 4 kV bus feeder breaker from the diesel generator would trip before the 4 kV load breaker due to the different sensitivities of the relays involved. This would only be a concern if a fire could cause two events; a fault on the control wiring of a 4 kV load which would cause the 4 kV load breaker to close (the 4 kV loads not involved with safe shutdown would not be energized if the diesel generator was the source of power and there was no accident condition) and then a specific fault on the power cable of the 4 kV load which would provide 5 to 17 amps of ground current.
We have identified all of the 4 kV loads not involved with safe shutdown and shown that the power and control wiring, except for three loads, are not
()
in the same fire area (other than the 4 kV switchgear rooms & a fire in this room would disable the whole bus) and thus a fire could not cause both power and control wiring to fail.
The three loads with power and control wiring in the same fire areas are Emergency Water Booster Pumps OAP163 and OBP163 and Emergency Cooling Water Pump OOP186.
A new ground overcurrent relay will be added to each of the two Emergency Service Water Booster Pumps.
The existing ground overcurrent relays on the Diesel Generator to 4 kV Emergency buses that feed these pumps will be replaced with new ground overcurrent relays.
For the Emergency Cooling Water Pump, the only area (other than the 4 kV switchgear room) where a fire could cause the pump to be energized and a fault to occur on the power feed would be in fire area 78B (General area, Turbine building). The power cables will be encapsulated in this area, thus a fire in this area will not affect both control and power cables.
Modifications The following modifications will be made to ensure proper coordination between breakers:
1)
Two new 4 kV relays will be added and two 4 kV relays will be replaced.
O 2)
Eight 4 kV relay settings will be changed.
5-3
3)
Seventeen 480 volt load center breaker settings will be changed.
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4)
Fifty four 480 volt motor control center magnetic only breakers will be replaced with new thermal magnetic breakers.
As per the guidelines in the letter from M. B. Fairtile to E. G. Bauer, Jr.,
dated 5/4/82, all of the new 480 volt thermal magnetic breakers will periodically be manually exercised and/or inspected to insure case of operation and on a rotating refueling outage basis a sample of these breakers will be tested to determine that breaker drift is within that allowed by the design criteria.
In addition the breaker design of the new 480 volt breakers will be factory tested to verify overcurrent protection as designed in accordance with the applicable standards.
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SE0 TION 6 i
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Fection 6 Tabulation of Modifications 1)
Modifications identified in the Safe Shutdown Analysis Zone Location Work to be Performed 4B RBCW Room Enclose Motor Control Center 20D11 within a 3-hour barrier, reroute ZD2Q1024K, ZDQ1027B Encapsulate 8 conduits 4C MG Set Room Reroute ZD2Q1024K, ZD2Q1027B Encapsulate many trays SE 2A Core Spray Reroute ZD2Q1024K SG Reactor Bldg. 116' Reroute ZD2Q1024K 5H Reactor Bldg. 135' Refer to text (Section 3) 5J Reactor Bldg. 165' Refer to text (Section 3) 12B RBCW Room One tray and 3 conduits (B) need to be encapsulated 12C MG Set Room Fix ZA3Q1827A-then encapsulate SSA raceways 13D 3C Core Spray Reroute or encapsulate ZB3Q1794A,B 13G Reactor Bldg. 116' Reroute or encapsulate ZB3Q1791A,B 13H Reactor Bldg. 135' Refer to text (Section 3) 13J Reactor Bldg. 165' Refer to text (Section 3) 13K Reactor Bldg. 195' Reroute control cables for 3A/B/C/DC 132 panels as required 49 Reactor Bldg. 195' 3A/B/C/DC 132 panels-reroute as required 6-1
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51 Reactor Bldg. 195' 2A/B/C/DC 132 panels-reroute as required 60 RCIC Room Reroute or encapsulate cables ZB2Ql800C,D, ZB2Q1785A, 1788A,B, 1789A, 1814A 62 HPCI Room Reroute or encapsulate cables ZA3Q1018B,C 63 RCIC Room Reroute or encapsulate cables ZB3Q1800C,B, ZB3Q2785A, 1788A,B, 1789A, 1814A 65A,B,C Rdwste. Bldg. 116' Reroute or encapsulate cables ZB3Q1799T, ZB301800C,D, ZA3Q1827A 72A Rdwste. Bldg. Gen.
Refer to text (Section 3) 72D Rdwste. Bldg. 116' Reroute or encapsulate cables ZB3Q1799T, ZB3Q1800C,D, ZA3Q1827A 75 Rdwste. Bldg. 135' Encapsulate six conduits 78A Turb. Bldg. 91' Encapsulate several 4 kV power feeds within 3-hour rated barriers 78B Turb. Bldg. Gen.
Encapsulate several 4 kV power feeds within 3-hour rated barriers 78E Counting Room Same as 78A,B 78H Cable Spread Room Refer to text (Section 3) 79 Turb. Bldg. 91' Encapsulate conduits ZA2B2349, ZC2B1249 80 Turb. Bldg. 91' Encapsulate conduits ZC3B137, ZC3B150, J17 82 HP Room Encapsulate several 4 kV conduits 108 Control Room Refer to text (Section 3) 6-2
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114 Turb. Bldg. 116' Same as 78A,B 117 3 B/D Batt.
Reroute or encapsulate conduit ZA3D002 118 3 A/C Batt.
Peroute or encapsulate ZB3D1802A,B 119 3C Swgr. Room Reroute or encapsulate seven conduits 120 3A Swgr. Room Relocate battery charger and reroute or encapsulate cables ZB3B1114A, ZD3DD01E 121 3D Swgr. Room Reroute or encapsulate cables ZC3A1702J, OG05H l
122 3B Swgr. Room Reroute or encapsulate cables ZC3A1506K, OGG3H 123 2D Swgr. Room Reroute or encapsulate cables ZC3A1701J, OG05H 124 2B Swgr. Room Redesign ZA2A1506K, OG03H, 2A170GR-then reroute or encapsulate same 125 2C Swgr. Room Redesign ZA1603R-then reroute or encapsulate same 126 2A Swgr. Room Relocate battery charger and reroute or encapsulate ZB2BD01E, ZDD01E, ZBOB6143C, ZB2B1122A 127 2 B/D Batt.
Peroute or encapsulate ZA2B1021A, ZA2B2022A, ZA2A1505A 128 2 A/C Batt.
Reourte or encapsulate ZB2D1802A,B t
130 Turb. Bldg. 91' Reroute or encapsulate ZA2B1249, ZA2B143, ZC2B1247 l
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132,133 Diesel Rooms Redesign, then encapsulate cables 2A1603J,K,L, 134,135 2A1706J,K,L, 3A1809 l
147 Turb. Bldg. 135' Encapsulate h SSA raceways General Encapsulate safety relief valve cables 4
j 6-3 i
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O General Redesign instrument loops for six variables per unit subject to 3-hour separation requirements General Upgrade penetration seals to required ratings as pre-viously committed in correspondence from J. W. Gallagher to D. G. Eisenhut dated October 14, 1981 2)
Modifications identified in the High Low Pressure Boundary Analysis Encapsulate control cables for MO2(3)-10-17 or MO2(3)-10-18 whenever both are within the same zone other than Main Control Roon.
3)
Modifications identified in the Associated Circuits Analysis Change the settings on the relays of the following 4 kV circuit breakers i
Unit 2 - 152-1505, 152-1705, 152-1806 l
Unit 3 - 152-1505, 152-1605, 152-1705, 152-1806 Change the sottings on the 4807 load center circuit breakers:
Unit 2 - 1013, 1014, 1021, 1022, 1113, 1121, 1122, 1221, 1222, 1321, 1322 Unit 3 - 1212, 1313, 1012, 1014, 1114 i
j Replace the following 480V motor control center magnetic-only circuit breakers with thermal magnetic circuit breakers:
Unit 2 - 3671, 3691, 3602, 3606, 3608, 3785, 3791, 3702, 3703, 5915, 5922, 5931, 5943, 6032, 6033, 6041, 3862, 3893, 3894, 3802, 3922, 3983, 3902, 3904, 2832, 2841, 2851 Common - 4955, 5055, 6131 Unit 3 - 3851, 3882, 3891, 3893, 3802, 3922, 3983, 3902, 3904, 2832, 2841, 2851, 3602, 3785, 3791, 3703, 5915, 5922, 5931, 5943, 5924, 6032, 6033 Add new ground overcurrent relays to the following 4 kV circuit breakers:
Unit 2 - 152-1609, 152-1709 Replace the existing ground overcurrent relays for the following 4 kV circuit breakers:
Unit 2 - 152-1606, 152-1704 Encapsulate the power feed conduit for the Emergency Cooling Water Pump in fire zone 78B Add fuses to the logic circuits to provide proper isolation for purposes of the safe shutdown analysis i
Add keylock control switches to 4 RHR pump circuit breakers to provide bypass to associated circuits 6-4 j
O O
O 4)
Modifications to the Emergency Lighting System Add eight hour battery power supply capability to the following locations:
Main Control Room Remote Shutdown Panels Cable Spreading Room (selected locations)
Four Emergency Switchgear rooms HPSW Pump bays Fifth bay in DG Building Access and egress routes within buildings for the above listed locations 5)
Schedule for completion of modifications Those modifications whose implementation requires plant shutdown will be performed at the next refueling outage for each unit currently scheduled for Spring 1983 (Unit 3) and Fall 1983 (Unit 2).
Those modifications whose implemen-tation does not require plant shutdown will be performed within nine months on Unit 2 and within nine months or before the end of the Spring 1983 refueling outage (whichever is last) on Unit 3.
This proposed implementation schedule represents our current estimation for completion of the work and may be revised at a later date for reasons beyond our control such as delays in material delivery or unforeseen technical problems.
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