ML20087A586
| ML20087A586 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 12/19/1991 |
| From: | Chris Miller Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20087A590 | List: |
| References | |
| NUDOCS 9201090239 | |
| Download: ML20087A586 (10) | |
Text
.
onnow o
UNITED STATES
[
3 c,, 'j NUCLEAR REGULATORY COMMISSION
- .h o R W ASHING TON. D. C. 20556 o.v t
s...../
PHILADELPHIA ELECTRIC COMPANY PUBLIC SERVICE EllCTRIC AhF DAY tDMPANY
~ DELMARVA POWER 7hD'llDWtDI@lW~~ ~
lTl AhTl t~ lli{,E L E,C T,P 1 C,,C OM,Ap Y DOCKET NO. 50-277 PEACH BUTTOM AT,0MIC Ppy,E,R,,STATjp!1,,,ppj{ Ng 2 AMENDMENT TO FAClllTY OPERATING LICENSE Amendment No. 165 License No. OPR-4A 1.
The Nuclear Regulatory Consnission (the Commission) has found that:
A.
The application for amendment by Philadelphia Electric Company, et.
al. (the licensee) dated July 2,1991, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I.
B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the connon defense and security or to the health or safety of the public; and C.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C(2) of Facility Operating License No. DPR-44 is hereby amended to read as follows:
9201090239 911239 fDR ADOCK 05000277 PDR 10
I
. (?)
Technical Specifications The Techniul Specifications contained in Appendices A and B, as revised through Amendment No.165, are hereby incorporated in the license. PECO shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION h h kY Charles L. Miller, Director Project Directorate I-2 L'.sision of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: December 19, 1991
L ATTACHMENT, TO, LJ CENS,E, AME!10!i!!q,!ip,.),65
{ACJ}.lT),0,PE,RATJNp,LJCENSE__ NO. OPR-44 DOCKET N0_.,5,0,-2,77 Replace the following'pages of the Appendix A. Technical Specifications with the enclosed pages. The revised areas are indicated by marginal lines.
Remove Insert 221-221 224 224 i
t
.. -. -. -. ~........
e uc...
LlHITING CONDl110NS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.9.C Emergency Service Water 4.9.C Emergency Service Water System System
- 1. The Emergency Service Water
- 1. The ESWS shall be tested System (ESWS) shall be operable once every 3 months as at all times when the reactor follows:
coolant temperature is greater than 212 F.
- a. Pump operability -
the pump shall be
- 2. If two ESW pumps become manually started and inoperable, the reactor flow capability tested may remain in operation in accordance with the for a period not to Section XI of the ASME exceed 1 month.
2?iler Pressure Vessel Code and applicable addenda
- 3. To consider the Emergency except where relief has Cooling Water pump operable been granted.
as an equivalent ESW pump, at least 1 ESW booster pump
- b. Valve operability -
and 2 Emergency Cooling Tower thc automatic valves fans must be operable.
shall be stroked individually from
- 2. The associated pump room available for normal operation f ans shall be tJted for except that a) one pump operability every 3 months, room supply and/or exhaust fan for each compartment
- 3. a. The Emergency Cooling may be out of service for Water pump and ESW one month or b) temporary booster pumps shall fans may be used in place of be tested once per permanently installed fans operating cycle to toprovideroomgemperatures verify operabilty.
at less than 120 f.
- b. The Emergency Cooling Tower fans shall be tested once per operating cycle to verify operability.
Amendment No. 165
-221-
PBAPS 4.9 B_ASES (Cont'd.)
Periodic tests between refueling outages verify the ability of the diesel generator to run at full load and the core and containment cooling pumps to deliver full flow.
Periodic testing of the various components, plus a functional test one-a-cycle, is sufficient to maintain adequate reliability.
Although station batteries will deteriorate with time, utility experience indicates there is almost no possibility of precipitous failure.
The type of surveillance described in this specification is that which has been demonstrated over the years to provide an indication of a cell becoming irregular or unserviceable long before it becomes a failure.
In addition, the checks described also provide adequate indication that the batteries have the specified ampere hour capability.
The station batteries shall be subjected to a performance test every third refueling outage and a service test during the other refueling outages.
This testing frequency complies with the testing requirements of the Institute of Electrical and Electronics Engineers (IEEE) Standard 450(1975), " Recommended Practice for Maintenance, Testing and Replacement of Lavge Lead Storage Batteries," and Regulatory Guide 1.129, Revision 1 (February 1978), " Maintenance, Testing and Replacement of Large Lead Storage Batteries for Nuclear Power Plants."
A performance test determines the ability of the battery to meet a specified discharge rate and duration based on the manufacturer's rating. A service test proves the capability of the battery to deliver the design requirements of the de systems; i.e., supply and maintain in operable status all of the actual emergency loads for the design basis accident. A performance test is the most severe test because the cycling on the battery at manufacturer's rating shortens the service life of the battery. A service test is performed at design load instead of manufacturer's ratings.
The diesel fuel oil quality must be checked to ensure proper operation of the diesel generators. Water content should be minimized because water in the fuel could contribute to excessive damage to the diesel engine. Amendment No. 131 centralized commitments related to Position C.2 of Regulatory Guide 1.137 Revision 1 (October, 1979) " Fuel Oil Systems for Standby Diesel Generators".
When it is determined that some auxiliary electrical equipment is out-of-service, the increased surveillance required in Section 4.5.F is deemed adequate to provide assuraece that the remaining equipment will be operable.
The test interval for the Emergency Service Water System, plus the ESW booster pumps, Emergency Cooling Tower fans,-and pump room fans associated with the ESW pumps is deemed adequate to provide assurance that the equipment will be operable based on good engineering judgment and system redundancy, plus the additional testing accomplished when the diesel generators are tested.
Pump flow tests during normal operation will be performed by measuring the head and flow in the system using suitable flow equipment and pressure instrumentation.
Amendment No. 131, 165
-224-
[pno,*o v
UNITED STATES
!" s m "k NUCLEAR REGULATORY COMMISSION
-t WASHINGTON, D. C. 20555 o(-
/
PHILADELPHIA ELECTRIC COMPANY PUBUC SERVICE ~llitThlt'AhF LAf tGMPANY DLLt1ARTA )DWER AND ChhTtDI4)Ahi
~
~AT[AhTlt CITY ELEtiklC COMPANY pp,CKETNO.50-278 PEACH B0TTOM ATOMJ,C,,P0,WER,5T,ATJ0N,, UNJT_pp.,3 d.M.Ep,0fgy,T,,Tp, fp CJ LJ Jy_0 P E R AT 1 H G L I C E N S E Amendment No. 169 License No. DPR-56 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Philadelphia Electric Company, rt.
al. (the licensee) dated July 2, 1991, complies with the standard, and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter 1.
B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health or safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Techni;al Specifications as indicated in the attachment to this license amendment, and paragraph 2.C(2) of Facility Operating License No. DPR-56 is hereby amended to read as follows:
. (2)
Technical, Specifications The Technical Specifications contained in Appendiws A and B, as revised through Amendment No. 169 ate hereby incorporated in the license.
PECO shall operate the facility in accor( nce with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Charles L. Miller, Director Project Directorate 1-2 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: December 19, 10)1
ATTACHMENT,TO LICENSE AMEppg pT,pp g g FACILITY OPERATING LICENSE NO. OPR-56 DOCKET !!0. 50-278 Replace the following pages of tt.e Appendix A Technical Specifications with the enclosed pages. The revised areas are indicated by marginal lines.
Remove psert 221 221 224 224 l
1 l
i e
f
f
~ ' '
rom.
l*
I LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3$9.CEmergencyServicoWater 4.9.C Emergency Service Water System System
- 1. The Einergency Service Water
- 1. The ESWS shall be tested System (ESWS) shall be operable once every 3 months cs at all times when the reactor follows:
coolant temperature i' greater than 212 F.
- a. Pump operability -
the pump shall be
- 2. If two ESW pumps Lv oma manually started and inoperable, the ieet:
tlow capabil'ty tested may remain in operation in accordance with the for a per'od not to Section XI of the ASME exceed 1 month.
Boiler Pressure Vessel Code and applicable addenda
- 3. To consider the Emergency except where relief has Cooling Water pump operable been granted.
as an equivalent ESW pump, at least 1 ESW booster pump
- b. Valve operability -
and 2 Emergency Cooling Tower the automatic valves fans must be operable.
shall be stroked individually from
- 4. To consider the ESW pump their control switches.
operable the associated pump room fans must be
- 2. The associated pump room available for ermal operation fans shall be tested for except that a) one pump operability every 3 months, room supply and/or exheust fan for each compartment
- 5. a. The Emergency Cooling may be out of service for Water pump and ESW one month or b) temporary booster pumps shall faris may be used in place of be tested onct per permanently installed fans operating cycle to toprovideroomgemperatures verify operabilty.
at less than 120 F.
- b. The Emergency Cooling Tower fans shall be tested once per operating cycle to verify operability.
Amendment No. 169
-221-1
Unit 3,
PBAPS 4.9 BASES (Cont'd.)
Periodic tests between refueling outages verify the ability of the diesel generator to run at full load and the core and containment cooling pumps to deliver full flow.
Periodic testing of the various components, plus a functional test one-a-cycle, is sufficient to maintain adequate reliability.
Although station batteries will deteriorate with time, utility experience indicates there is almost no possibility of precipitous failure.
The type of surveillance described in this specification is that which has been demonstrated oser the years to provide an indication of a cell becoming irregular or unserviceable long before it becomes a failure.
In addition, the checks described also provide adequate indication that the batteries have the specified ampere hour capability.
The station batteries shall be subjected to a performance test every third refu211ng outage and a service test during the other refueling outages.
This testing frequency complies with the testing requirements of the Institute of Electrical and Electronics Engineers (IEEE) Standard 450(1975), " Recommended Practice for Maintenance. Testing and Replacement of Large Lead Storage Batteries," and Regulatory Guide 1.129, Revision 1 (February 1978), " Maintenance, Testing and Replacement of Large Lead Storage Batteries for Nuclear Power Plants."
A performdnce test determines the ability of the battery to meet a specified discharge rate and duration based on the manufacturer's rating. A service test proves the capability of the battery to deliver the design requirements of the de systems; i.e., supply and maintain in operable status all of the actual emergency loads for the design basis accident. A performance test is the most severe test because the cycling on the battery at manufacturer's rating shortens the service life of the battery. A service test is performed at design load instead of manufacturer's ratings.
l The diesel fuel oil quality must be checked to ensure proper operation of the diesel generators. Water content should be minimized because water in the fuel could contribute to excessive damage to the diesel engine. Amendment No. 134 centralized commitments related to Position C.2 of Regulatory Guide 1.137, Revision 1 (October, 1979) " Fuel Oil Systems for Standby Diesel Generators".
When it is determined that some auxiliary electrical equipment is out-of-service, the increased surveillance required in Section 4.5.F is deemed adequate to provide assurance that the remaining equipment will be operable.
The test interval for the Emergency Service Water System, plus the ESW booster pumps, Emergency Cooling Tower fans, and pump room fans associated with the ESW pumps is deemed adequate to provide assurance that the equipment will be operable based on gord engineering judgment and system redundancy, plus the additional testing accomplished when the diesel generators are tested.
Pump flow tests during normal operation will be performed by measuring the head and flow in the system using suitable flow equipment and pressure inst. entation.
Amendment No. Z05, ZH, 169
-224-