ML20236D246
| ML20236D246 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 07/27/1987 |
| From: | Martin R Office of Nuclear Reactor Regulation |
| To: | Alden W PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| References | |
| NUDOCS 8707300373 | |
| Download: ML20236D246 (6) | |
Text
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k I..Y E Docket Nos.:
50-277 50-278 I
l Mr. William M. Alden Engineer-In-Charge-Licensing
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Philadelphia Electric Company 2301 Market Street Philadelphia, Pennsylvania 19101 l
Dear Mr. Alden:
1 l
Our meeting at the Peach Bottom Atomic Power Station Site on July 30, 1987 I
will consider routine licensing issues in the staff's plant systems area of review. Enclosed is a draft of the agenda for the fire protection portion of the meeting.
N i
Robert E. Martin, Project Manager l
Project Directorate I-2 I
Division of Reactor Projects I/II Enclosure-As stated 1
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jg( t ? W Docket Nos.: 50-277 50-278 Mr. William M. Alden Engineer-In-Charge-Licensing Philadelphia Electric Company 2301 Market Street 4
Philadelphia, Pennsylvania 19101
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Dear Mr. Alden:
Our meeting at the Peach Bottom Atomic Power Station Site on July 30, 1987 will consider routine licensing issues in the staff's plant systems area of review. Enclosed is a draft of the agenda for the fire protection portion of the meeting.
Ro ert E. Martin, Project Manager Project Directorate I-2 Division of Reactor Projects I/II
Enclosure:
As stated i
4
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10 CFR Part 50, Appendix R Review for Peach Bottom, Units 2 and 3 Docket Nos. 50-277/278 References 1
1.
Licensee's subr'
.s on Appendix R compliance for Peach Bottom Nuclear Units 1.
Fire Protection Program - September 30, 1986.
2.
Compensatory Measures for Conditions of Non-Compliance with Appendix R
- October 24, 1986.
3.
Justification for Continued Operation (JCO) of Peach Bottom Nuclear Units with conditions of Non-Conformance with Appendix R - November j
28, 1986.
4.
Fire Protection Program - January 8, 1987.
II. Letter from Director, DRS, Region I to the Licensee 5.
Status of compliance with Appendix R at Peach Bottom Nuclear Units -
February 20, 1987.
I During our site visit on July 30, 1987, we wish to discuss the following items relating to the Fire Protection Program at the Peach Bottom Nuclear Units:
A.
Conditions of Non-Compliance with Appendix R Referencet 3, 4 and 5 have listed these conditions and the proposed Interim Compensatory Measures (ICMs) until the permanent modificaticro are completed.
Reference 5 has concluded that the proposed ICMs are j
acceptable. Our review of References 3 and 4 and our contractor's (Brookhaven National Laboratory) Technical Evaluation indicates that the information provided by the licensee on proposed permanent modifications is incomplete.
So, we will seek descriptions of the modifications underlined and listed below during our site visit:
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1.
Power Source which survives an Appendix R fire, relocation or installation of instruments and protection of cables for preventing the adverse condition listed below:
a.
Loss of process and diagnostic rtaitoring instrumentation -
1 Fire Areas (FAs) 2,13N and 6S.
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2.
Control Circuitry chanoes for preventing the adverse conditions listed:
a.
Blown control power fuse for ESW-FAs 43, 44, 45 and 46.
I b.
Blown control power fuse for ESW/ breaker lockup-FAs 37-39, 48 and 50.
c,,
No RHR minimum RHR flow protection - FAs 6S and 13N d.
Closure of ESW discharge valve - FAs 2, 25, 34, 36 and 43.
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3.
Ret outing the applicable control cables for preventing the adverse conditions listed below; a.
Loss of Unit 2 relief valve operability - FAs 6S and 6N b.
Feedwater block valve closure - FA 25 4.
Installation of local controllers for preventing the adverse conditions listed below; a.
Spurious closure of HPCI and RCIC steam line inboard isolation valves - FAs 6S and 13N b.
RCIC isolation valva closure - FA 6N 5.
New instrument loop to prevent the adverse condition listed below:
a.
Loss of CST Water level indication - FA 50 6.
Installation of Trip Circuits to prevent the adverse condition listed:
a.
Inability to isolate HPCI - FA 13N b.
Inability to isolate RCIC - FA 25
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j 7.
Sealing of man-hole covers to prevent the adverse condition listed:
a.
Intrusion of combustible liquid caused by inadequate separation between. redundant HPSW/ESW pumps - FAs 50, yard b.
Same as above caused by inadequate separation between redundant diesel generator cables - FA yard.
8.
Long-term air supply to prevent the adver_se condition listed:
a.
Loss of Unit 2 relief valve operability - FA 6S i
9.
Permanent backup nitrogen supply to prevent the adverse condition listed:
I t
a.
Damage to parallel air headers for SRV operation - FA 13S 10.
Electrical overcurrent coordination to prevent the adverse condition-listed:
a.
Loss of HPCI MCC 20 D 11/ 20 0 11A coordination - FA 6S 11.
Protection of applicable cables to prevent the adverse conditions listed:
a.
Trippling of RHR pump breaker - FAs 35, 36 and 37 - 3 cables b.,
Blown 1c'31c power fuse for core spray - FA 2 - 2 cables
'l' ',
c.
RHR pump breaker logic trip / lock up - FA 34 - 2 cables d.
Spurious Co, injection in DG compartments - FAs 44, 45, 46 and 54 - 4 control cables HPCI spurious isolation cignal - FA 135 - 2 control cables e.
i f.
Operation of bus. differential relay - FA 34, 35, 36 and 37 - 4 cables g.
Loss of core spray flow indication - FA 2 - 1 instrumentation cable h.
Loss of RHR/HPSW flow indication - FA 30 - 2 power cables
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1.
Loss of power for DG auxiliary MCC - FA 6N - 1 power cable
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,i.
Loss of torus temperature indication - FA 13N - one instrumentation cable k.
Loss of RHR flow indications - FA 4 - 1 instrumentation cable 1.
Loss of Process indication - FA 6N - all required instrumentation cables We will be additionally seeking information regarding the following:
1.
Availability of fire detectors and automatic fire suppression systems as required by Appendix R,Section III.G.2.C for all the areas listed under Modification 11.
2.
Safety Analyses for all modifications listed above to demonstrate that these modifications will not adversely impact any safety-related system, equipment or component.
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B.
Alternative Safe Shutdown Procedure SE-10 With regard to the above, we will discuss the following items:
a.
current status of SE-10 b.
Identification of all the manual actions c.
The time frames after scram for completing the various manual actions.
The time-line manual actions may be identified in a separate document.
d.
Minimum time frame after scram before which a few manual actions may require completion; number of such manual actions; brief descriptions of such actions.
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. l C.
High/ Low Pressure Interfaces I
Licensee's submittals exclude fire-induced breaches of some high/ low pressure interfaces as " incredible". We will seek supporting analyses I
performed taking into consideration the positions outlined in Generic Letter 86-10, Section 5.3.1 for"each of the omitted interfaces to demonstrate the validity of their eiclusions. Alternately, we will seek identification of the corrective measures for each of the omitted-interfaces.
D.
Shutdown Method C We will discuss the following items with regard to the above:
I
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Compliance with NUREG-0783 for suppression pool local temperature a.
limit during steam discharge into the pool.
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b.
Adequacy of available NPSH for the RHR pump.
E.
Miscellaneous Our discussion may also include the following items:
a.
High Inpedance concerns corrective measures for electrically-operated breakers associated l
with non-safe shttdown loads supplied by a common bus that supplies power to safe shutdown loads.
b.
Electrical Isolation Deficiency corrective measures in case local and remote control circuits for hot shutdown equipment or component share a common fuse (both interim and long-term measures) c.
Hot and cold shutdown repairs Identification of such repairs if applicable.
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1 d.
Man Power Needs Available on-site man power excluding fire brigade crew I
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