ML20028D045
| ML20028D045 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 01/12/1983 |
| From: | Daltroff S PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | Eisenhut D Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8301140433 | |
| Download: ML20028D045 (10) | |
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PHILADELPHIA ELECTRIC COMPANY 23ol MARKET STREET P.O. BOX 8699 PHILADELPHI A. PA.19101 SHIELDS L D ALTROFF ELECTR C PR C710N January 12, 1983 Re: Docket Fos. 50-277 50-278 Mr. Darrell G. Eisenhut Division of Licensing U.S. Nuclear Regulatory Commission Washington, DC 20555
SUBJECT:
Request for an Exemption to the Appendix R Schedule on Fire Protection for Peach Bottom Atomic Power Station
Dear Mr. Eisenhut:
This letter requests, pursuant to Section 50.12 of the Commission's regulations, exemptions to the implementation schedules identified in 10 CFR 50.48, subsections (c) (2) and (c) (3) for several of the modification commitments presented in the Fire Protection Safe Shutdown Report - Peach Bottom Atomic Power Station Units 2 and 3.
The report was transmitted by correspondence dated June 28, 1982, (S. L. Daltroff, PECo to D.
G. Eisenhut, NRC).
Additionally, this letter makes several minor revisions in the modification commitments presented in section 6 of the referenced report to reflect a re-evaluation of the Peach Bottom safe shutdown analyses.
Most of the modifications identified in the referenced report submitted June 28, 1982, are expected to be completed in accordance with the schedule provisions of Section 50.48, subsections (c) (2) and (c) (3), as modified by the exemption granted in correspondence dated May 4, 1982, (M. B. Fairtile, NRC to E. G. Bauer, PECo).
The modifications for which an exemption to the implementation schedule is requested are as follows:
i 8301140433 830112 pM ADOCK 05000277 i
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Mr. D.-G..Eisenhut-Page 2
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Modifications Replace ~ fifty-fourJ480 V. motor control center magnetic-only circuit breakers.with. thermal magnetic circuit breakers to establish' proper coordination-between breakers.
Reason'for Delays Circuit breakers that meet'the
- equipment qualification standards and'are. adaptable.to the Peach: Bottom breaker compartment are not currently available on the market.
We are making the necessary-arrangements to have the_ qualification testing performed.. The qualification processf s expected to be i
completed by the fall, 1983.
Exemption requested:'The following implementation; schedule is requested for this modification:
a)
Outage work: First refueling outage or planned outage that lasts at least-60 days, commencing after January 1, 1984.
b)
Non-outage work: March 31, 1984.
2.
Modification: Add keylock control switches to 4 RHR pump circuit breakers to provide bypass to associated circuits.
Reason for Delay: Equipment may not be available in time to implement the modification on the Unit 3 refueling outage scheduled to start February 12, 1983.
Exemption Requested: Revise the schedule to permit implementation during the first refueling outage or planned outage that lasts at least 60 days, commencing after May 31, 1983.
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Mr. D. G. Eisenhut
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Modifications:
- a)
Rede' sign' instrument loops'for six variables'per unit subjectLto 3 hour3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> separation requirements.
b)
Encapsulate control cables for. shutdown. cooling.
valves (MO-10-17 and.MO-10-18) whenever both are withinithe same zone:other;than main' control room.-
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.c)
Add fuses to the logic circuits to provide proper isolation-for purposes of the safe shutdown-analysis.
Reason for Delay: These modifications _ involve the' isolation of. redundant electrical circuits-in the cable spreading room. ' Modification' (b) also. involves i
separation of cables in the remote shutdown panel-area.
Currently, an exemption request to the separation ~
criteria of 10'CFR 50, Appendix R, paragraph III.G.2 is pending NRC review for both the cable spreading room and remote shutdown panel. area.
The exemption request for these areas was identified in Section'3 of the Fire i
Protection Safe Shutdown Report - Peach Bottom Atomic Power Station Units 2 and 3 (submitted June 28,.1982).
Since the NRC ruling on the exemption request impacts the separation design for electrical circuits involved-with these three modifications, it would be more appropriate to consider these modifications _under-the scope of the cable spreading room and remote shutdown panel area exemption requests and alternative design features.
Exemption Request: As previously reported to the NRC, we have obtained the services of a fire protection consultant to identify proposed alternative design features to those required by the Appendix R separation criteria for the shutdown equipment in the control room, csble spreading room, and remote shutdown panel area.
A description of the alternative design features, and a technical justification supporting the exemption request will be submitted for your consideration by January 31,
'1983.
The a".bmittal will also propose a schedule for-implementation of all alternative design features associated with the exemption requests for these areas, i
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Mr. D. G. Eisenhut Page 4 including a revised schedule for the three modifications described above.
We therefore propose that the implementation schedules for the subject modifications be superseded by the schedule to be identified in the January 31, 1983 submittal.
The June 28, 1982, report identified a commitment to encapsulate the power feed conduit for the emergency cooling water pump in fire zone 78B.
A re-evaluation revealed that the pump is fed by a method B electrical bus, and the power cable is routed only through method B fire zones from the bus to the pump.
Encapsulation of these power cables is therefore not necessary and should be deleted from the modification commitments identified in the June 28, 1982 report.
Additionally, the report committed to the redesign of instrument loops for six variables to establish proper separation.
The variables originally contemplated were reactor temperature, reactor pressure, reactor level, torus level, torus temperature, and containment pressure.
The reactor temperature is not an essential variable needed for Boiling Water Reactors due to the nature of its concept.
Therefore, we propose excluding this variable from the fire protection separation criteria and limiting the modification to the other five variables.
The attachment to this letter provides a revised Section 6 to the June 28, 1982 report.
The revisions correct typographical errors and add additional cables requiring reroute or encapsulation, as indicated by a vertical bar in the margin.
Recent improvements in the Peach Bottom fire protection program, as well as the fire retardant characteristics of electrical cables selected for installation in the facility, provides sufficient compensatory measures to ensure safe shutdown capability until such time a final design can be implemented.
The improvements include additional suppression systems, and a new early warning detection system in all areas which present an exposure fire hazard to safety related systems.
The new systems provide protection for twenty-one additional areas in each unit, and improves the protection in five other areas.
The new early warning detection system, as well as the improvements in fire protection training, will ensure a prompt response to a fire by the fire brigade to mitigate the extent of damage to safety
Mr. D. G. Eisenhut' Page 5 related equipment..The extensive.use of fire retardant electrical cable at Peach ~ Bottom is an. inherent design' feature that would prevent a fire of the type that occurred at Browns Perry.
For these reasons, the requested schedule change is
. appropriate and will.not endanger the health and. safety of the public.
Should you have any questions or require additional information regarding this matter, please do not. hesitate to contact us.
Very truly yours, Attachment cc:
Site. Inspector Peach Bottom
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ATTACEv217f Docket Nos. 50-277 50-278 Section 6 Tabulation of Modifications 1
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Modifications identified in the Safe Shutdown Analysis Zone Location Work to be Performed 4B RBCW Room Enclose Motor Control Center 20D12 within a 3-hour barrier, l
rerOate ZD2Q1024K, ZDQlO27B Encapsulate sc=e conduits and junction boxes l
4C MG Set Room Reroute ZD2Q1024K, ZD2Q1027B Encapsulate many raceways and junction boxes l
SE 2A Core Spray Reroute ZD2Q1024K SG Peactor Bldg. 116' Reroute ZD2Q1024K 51f Reactor Bldg. 135' Refer to text (Section 3)
SJ 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 and junction boxes l
13D 3C Core Spray Reroute or encapsulate ZB3Q1794A,B 13G Peactor Bldg. 116' Reroute or encapsulate ZB3Q1794A,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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7 51 Feactor Bldg. 195' 2A/B/C/DC 132 panels-reroute as required
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.60 RCIC Room Reroute or encapsulate cables ZB2Q1800C,D, ZB2Q1785A,
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1788A,B, 1789A, 1814A.
62 HPCI Room Reroute or encapsulate cables ZA3Q1018B,C.
63 RCIC Room Reroute or encapsulate, cables - ZB3Q1800C,I),~ SB3Q2785A,
- l, 1788A,53, 1789A, 1814A-65A,B,C Rdwste. Bldg. 116' Eeroute or encapsulate cables ZB3Q1799T,'ZB3Q1800C,D,.
ZA3Q1827A 72A Rdwste. Bldg. Gen.
Refer to text (Section 3) 72D Rdwste. Bldg. 116' Reroute or encapsulate cables ZB3Q1799T, ZB3Q1800C,D, ZA3Ql827A
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75 Edwste. Bldg. 135' Encapsulate seven conduits; reroute or encapsulate ZA3Q1827A '
l 78A Turb. Bldg. 91' Encapsulate several 4 kV power feeds and junction boxes-within 3-hour l reted barriers 78B Turb. Bldg. Gen.
Encapsulate.several4kVpowerfeedsandjunctionboxeswithin3-hour l~
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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 and one junction box l
l 108 '
Control Room Refer to text (Section 3)
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114 Turb. Bldg. 116' Same as 78A,B 117 3 B/D Batt.
Reroute or encapsulate conduit ZA3D002 and ZA3M2416 l
118 3 A/C Batt.
Reroute or encapsulate ZB3D1802A,B l
119 3C Swgr. Room Reroute or encapsulate six conduits 120 3A Swgr. Room Relocate battery charger and reroute or encapsulate cables ZB3B1114A, ZD3DD01E and ZB3BI)01 l
121 3D Swgr. Room Reroute or encapsulate cables ZC3A1702J, OG05H 122 3B Swgr. Room Reroute or encapsulate cables ZC3A1506K, OG03H 123 2D Swgr. Room Rerotte or encapsulate cables ZC3A1702J, OG05H l'
124 2B Swgr. Room Redesign ZA2A1506K, OG03H, 2A1706R-then reroute or
.l cncapsulate same 125 2C Swgr. Room Redesign ZA1603R-then reroute or encapsulate same 126 2A Swgr. Room Relocate battery charger and reroute or encapsulate ZB2BD01E, ZD2D01E,ZBOB6143C, ZB2B1122A l
127 2 B/D Batt.
Reroute or encapsulate ZA2B1021A, ZA2B1022A, ZA2A1505A l
128 2 A/C Batt.
Reroute or encapsulate ZB2D1802A,B l
130 Turb. Bldg. 91' Reroute or encapsulate ZA2B1249, ZA2B143, ZC2B1247 132,133 Diesel Rooms Redesign, then encapsulate cables 2A1603J,K,L, 134,135 2A1706J,K,L, 3A1809 147 Turb. Bldg. 135' Encapsulate SSA raceways General Encapsulate safety relief valve cables 6-3 i
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U 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 sare zone other than Main Control Room.
3)
Modifications identified in the Associated Circuits Analysis Change the settings on the relays of the following 4 kV circuit breakers Unit 2 - 152-1505, 152-1705, 152-1806 Unit 3 - 152-1505, 152-1605, 152-1705, 152-1806, 152-1505, 152-1609, 152-1805-l Change the settings on the 480V load center circuit breakers:
Unit 2 - 1013, 1014, 1021, 1022, 1113, 1121, 1122, 1221, 1222, 1321, 1322 Unit 3 - 1213, 1313, 1013, 1014, 1114, 1113 l
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, 3882, 3893, 3894, 3802, 3922, 3983, 3902, 3904, 2832, 2841, 2851 Cormon - 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-Add keylock control switches to 4 RHR pump circuit breakers to provide bypass to associated circuits 6-4
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Modifications to the Emergency Lighting System t
Add eight hour battery power supply capability to the following locations:
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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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