ML19332F086
| ML19332F086 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 12/04/1989 |
| From: | Butler W Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19332F084 | List: |
| References | |
| NUDOCS 8912130380 | |
| Download: ML19332F086 (18) | |
Text
{{#Wiki_filter:, e NO r C ~ g j '- ?,f UNITED STATES I l.. ~V tt g NUCLEAR REGULATORY COMMISSION _ Ea i[ WASHINGTON, D. C. 20555 \\,...../ e 1 PUBLIC SERVICE ELECTRIC A GAS COMPANY PHILADELPHIA ELECTRIC COMPANY DELMARVA POWEP AND LIGHT COMPANY. ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-272 SALEM GENERATING STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE y ;; b! "bo 0 -70 1.- The Nuclear Regulatory Connission (the Commission or the.NRC) has found that' A. The application for amendment #iled by the Public Service Electric & ) Gas Company, Philadelphia Electric Company, Delmarva Power and Light Company and Atlantic City Electric Company (the licensees) dated 'i March 23,'1989 and supplemental letters dated April 14, 1989, August 25, 1989, September PP, 1989 and October 26, 1989 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 j 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 i ) this amendment'can be conducted without endangering the' health and-J safety of the public, and (ii) that such activities will be conducted ') l. in compliance with'the Commission's regulations set forth in 10 CFR -i Chapter I;- i D. The. issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and q F. The issuance of this amendment is in accordance with 10 CFR Part 51 of ' r' the Consnission's regulations and all applicable requirements have been satisfied. o 3 2. Accordinolv, the license is amended by changes to the Technical Specifica-f tions as indicated in the attachment to this license amendment, and L paragraoh 2.C.(2) of Facility Operating License No. DPR-70 is hereby j amended to read as follows: 8912130380 891204 i ADOCK0500g2 DR 4
w l:: 1 i. -(2) Technical Specifications and Environmental-Protection Plan
- l The Technical. Specifications contained in Appendices A and B, as revised through Amendment No. 105 are hereby incorporated.in the-t license.
The licensee shall operate the facility in accordance with-the Technical Specifications. 3. 'This license anendment is effective as of'its date of issuance and shall. be implemented before startup from the ninth refueling outage, currently scheduled for Fall, 1990. FOR THE NUCLEAR REGULATORY COMMISSION (l{ b ,( Walter R. Butler, Director Project Directorate I-2 Division of Reactor Projects I/11
Attachment:
Changes to the Technical Specifications Date of Issuance: December 4, 1989 l i 1 l t-l l 1 l-L
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v 1,4 . ~r. 7- + ' ATTAC' MENT TO LICENSE AMENDMENT NO, 105 H FACILITY OPERATING LICENSE NO. OPR-70 DOCKET NO. 50-272 Revise AppendixLA as follows: \\ Remove Pages Insert Pages-VIII VIII' o XII: XII' , o-XIV' XIV '3/4.8-14 t-3/4 8-15 B 3/4 8-1 B 3/4 8-1 B 3/4'8-2 >l l') N 1 L l .l 0 .1 l 1. l l l '.3 -
p-- W 3 TNDEX s: = LIMITING CONDITIONS FOR'0P?FATION AND SURVEILLANCE REQUIREMENTS 1,. ..........................c...,. SECTION PAGE-p 3/4.8 ' ELECTRICAL POWER SYSTEMS 13/4.8.1-A. C. SOURCES Operating 3/4 8-1 i Shutdown 3/4 8-5 3/4.8.2 ONSITE POWER DISTRIBUTION SYSTEMS A.C. Distribution - Operating. 3/4 8-6 A.C. Distribution - Shutdown 3/4 8-7 -125-Volt D.C. Distribution - Operating 3/4 8-8 125-Volt D.C. Distribution - Shutdown. 3/4 8-10 28-Volt D.C. Distribution - Operating. 3/4 8-11
- 28-Volt D.C. Distribution - Shutdown 3/4 8-13 3/4.8.3 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES.
3/4 8-14 (f s 1 [ r SALEM - UNIT 1 VIII Amendment No.105 l e I
, =. _ 4:e IVDEX n / * ;9 a r .,4. 'st -. 1 n . BASES' a [ -SECTION-PAGE' L 3/4.3 INSTRUMENTATION ,3 / 4. f.1 - PROTECTIVE INSTRUMENTATION. B 3/4-3-1 -) 3/4.3.2~ ENGINEERED SAFETY FEATURES (ESF) INSTRUMENTATION B'3/4 3-11 ( e 3/4.3.1. MONITORING INSTRUMENTATION ~.-. B 3/4'3-1 L. 3/4.4 REACTOR COOLANT SYSTDi n y 3/4.4.1-REACTOR COOLANT LOOPS AND COOLANT ~l CIRCULATION B 3/4 4-1 l -3/4.4.2 SAFETY VALVES B 3/4 4-la ,I a '3/4.4.3 RELIEF. VALVES B 3/4'4-la 3/4.4.'4 PRESSURIZER B-3/4 4-2 l .3/4.4;5 STEAM GENERATORS., B 3/4 4-2 i 3/4.4.6 - REACTOR COOLANT SYSTEM LEAKAGE. P 3/4 4-3 j 3 / 4'. 4. 7 CHEMISTRY B 3/4'4-4 I 7E 1/4.4.8 SPECIFIC ACTIVITY B-3/4 4-5 l 1 .3/4.4.9' ' PRFSSURE/ TEMPERATURE LIMITS .B 3/4 4-6 s 3/4.4.10 STRUCTURAL INTEGRITY B 3/4 4-11 l
- 3/4.4.11 INTENTIONALLY BLANK.
. B 3/4 4-11 1 3/4.4.12 HEAD VDITS. B 3/4 4-11 I v i i d I 1 SALEM - UNIT 1 XII Amendment No.105 t 1
.g. .c E NDEX y .'p. - U <s.- BASES p j-SECTION' PAGE I 3/4.7 PLANT SYSTEMS 3/4.7.1 TURBINE CYCLE.. B 3/4'7-1 L3/4.7.2 SliAM GENERATOR PRESSURE / TEMPERATURE LIMITATION. B 3/4 7-4 3/4.7.3. COMPONENT COOLING WATER SYSTEM B 3/4 7-4 3/4.7.4 SERVICE WATER SYSTEM . B 3/4 7-4 3/4.7.5 FLOOD PROTECTION. . B 3/4 7-5 j .3/4.7.6 CONTROL ROOM EMERGENCY AIR CONDITIONING SYSTEM, . B 3/4 7-5 3/4.7.7 AUXILIARY BUILDING EXHAUST AIR FILTRATION SYSTEM. . B 3/4 7-5 '3/4.7.8 SEALED SOURCE CONTAMINATION. . B 3/4 7-5 I 3/4;7.9 SNUBBERS . B 3/4 7-6 I 3/4.'7.10. FIRE SUPPRESSION SYSTEMS ...... B 3/4 7-7 3/4.7.11 PENETRATION FIRE BARRIERS . B 3/4 7-7 3/4.8 ELECTRICAL POWER SYSTEMS ~3/4.8.1 A. C. SOURCES and. AND 3/4.8.2 ONSITE POWER DISTRIBUTION SYSTEMS. . B 3/4 8-1 3/4.8.3 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES. . B 3/4 8-1 l U 0 i l i SALEM - UNIT 1 XIV Amendment No.105 4
5' ~ .l w '. e E'LICTRICAL POWER SYSTEMS-3/4.8.3 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES LIMITING CONDITION FOR' OPERATION 3.8.3.1 All containment penetration conductor.overcurrent protective devices l required to provide thermal protection of penetratior.s shall be OPERABLE. .- APPLICABILITY:; MODES 1, 2, 3 and-4. i 1 ACTION: With one or more of the required containment penetration conductor overcurrent protective device (s) inoperable: l Restore'the protective device (s) to OPERABLE status or de-energize -{ a. the circult(s) by tripping either the primary or backup protective i device,-or racking out or removing the primary or backup device within 72 hours, declare the affected system or component inoperable, and verify the primary or backup protective device-to be .l tripped, or the primary or backup device racked out or removed at least once per 7 days thereafter; the provisions of Specification I 3.0.4 are not applicable to overcurrent devices in circuits which have their primary or backup protective device tripped, or which have the primary or backup device racked out or removed, or b. Be in at least HOT STANDBY within the next 6 hours and in COLD i SHUTDOWN within the following 30 hours. SURVEILLANCE REQUIREMENTS 4.8.3.1 All' required containment penetration conductor overcurrent protective = devices shall be demonstrated OPERABLE: a. At least once per 18 months: 1. For at least one 4.16 KV reactor coolant pump circuit, such that all reactor coolant pump circuits are demonstrated OPERABLE at least once per 72 months, by performance of: (a) A CHANNEL CALIBRATION of the associated protective relays, and i (b) An integrated system functional test which includes simulated automatic actuation of the system and verifying g that each relay and associated circuit breakers and control circuits function as designed. SALEM - UNIT 1 3/4 8-14 Amendment No.105
g re t9- ~~ Y'i ELECTRICAL PO'*'ER SYSTEMS '
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' SURVEILLANCE REOUTREMENTS (Continued) 2. By verifying the.0PERABILITY,of the' required molded case and [' lower voltage circuit breakers, by selecting and functionally testing a. representative sample of at least 10% of all the circuit breakers of;that type. Circuit breakers selected for functional testing shall be selected on a rotating basis. The . functional test shall consist'of injecting a current input at >the specified setpoint to each selected circuit breaker and verifyingLehat each circuit' breaker functions as designed'. Circuit breakers found-inoperable during functional testing-shall be restored.co OPERABLE status prior'to resuming operation. For each circuic breaker found inoperable during the functional tests, an additional representative sample'of at least.10% of all the circuit breakers of the inoperable type-shall also be functionally tested:until-no more failures are found or all circuit breakers of that type have been functionally tested. .l b. -At least once per 60 months by subjecting each circuit breaker to an inspection and preventive maintenance in accordance with procedures prepared in conjunction with its manufacturer's recommendations. g- -s I SALEM UNIT 1 3/4 8 15 Amendment No.105 1
m-W (m 3/4.8 F7FCTRICAL POVER SYSTEMS, ~ F e p 1AREE 3/4.8.1 AND 3/4.8.2 A.C. SOURCES AND ONSITE POWER DISTRIRUTION SYSTEMS ~ N' The'0PERABILITY of the A.C. and D.C. power sources and associated . distribution systems'during operation ensures that sufficient power will be available to supply the safety related equipment required for 1) the safe shutdown of the facility and 2) the mitigation and control.of accident 5 conditions within-the facility. The minimum specified independent and redundant A.C.;and D.C. power sources and distribution systems satisfy the requirements of General Design Criterion 17 of Appendix "A" to 10 CFR Part 50. _l_' The ACTION requirements specified for the levels of degradation of the power sources provide restriction upon continued facility operation commensurate with the level of degradation. The OPERABILITY of the power sources are consistent with the initial condition assumptions of the accident m . analyses and are based upon maintaining at least one of each of the onsite A.C. and D.C. power sources,and associated distribution systems OPERABLE j during accident conditions coincident with an assumed loss of offsite power j and single failure of the other onsite A.C. source. The OPERABILITY.of the minimum specified A.C. and D.C. power sources and associated distribution systems during shutdown and refueling ensures that 1) the facility can be maintained in the shutdown or refueling condition for extended time periods and 2) sufficient instrumentation and control capability is available for monitoring and maintaining the facility status, ) i 3/4.8.3 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES-Containment electrical penetrations and penetration conductors are protected by either deenergizing circuits not. required during reactor operation or by demonstrating the OPERABILITY of primary and backup ) overcurrent protection circuit breakers during periodic surveillance. Thu surveillance frequency applicable to molded case circuit breakers and lower voltage circuit breakers provides assurance of breaker reliability by testing at least one representative sample of each manufacturer's brand of molded case - and lower. voltage circuit breakers. Each manufacturer's molded { case circuit breakers and lower voltage cirecit breakers are grouped into representative samplos which are then tested on a rotating basis to ensure that all breakers are tested. If a wide variety exists within any i manufacturer's brand of molded case or lower voltage circuit breakers, it is i necessary to further divide that manufacturer's breakers into groups and creat each group as a separate type of breaker for surveillance purposes. l L l sal.EM UNIT 1 B 3/4 8-1 Amendment No.105 e
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4 ELECTRICAL' PO'**ER SYSTEMS - .u io BASES'(Continued) . A list. of the' required containment. penetration conductor overcurrent protective-devices, with-information on location, size and equipment powered-by the-protective circuit is mainteined in the UFSAR. TheElist is limited to
- thoseiovercurrent devices installed for the purpose of keeping circuit -fault
/ current below the penetration rating. It does not apply to other overcurrent idevicestwhich protect penetrations where fault' currents are:less than.the. 't Y". sustained' rating of-the penetration. This is consistent with.the requirements ~ of-IEEE 741'1986 which states that no special consideration.is required to
- protect electrical penetrations ~that'can, indefinitely, withstand the maximum.
- 4 fault' current available..Setpoints are controlled by plant procedures and
' drawings ~and any additions,- deletions or modifications to the containment - 1 . penetration conductor overcurrent protective' devices list is governed by .Section 50,59 of 10 CFR Part 50. t 5 ( L g 1 i, i l D l SALEM - UNIT 1 B 3/4 8-2 Amendment No.105 l. h sin
(t. 4 4 4" 'o 1 [I 1,;g . NUCLEAR REGULATORY COMMISSION . UNITED STATES E WASHINo TON, D. C. 20555 \\.....} PUBLIC SERVICE ELECTRIC & GAS COMPANY l PHILADELPHIA FLFCTRIC COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-311 l i SALEM GENERATING STATION, UNIT NO 2 l l AMEN 0 MENT TO FACILITY OPERATING LICENSE Amendment No.82 License No. DPR-75 1. The Nuclear Reculatory Commission (the Conunission or the NRC) has found l that: [ ] 'A. The application for amendment filed by the Public Service Electric & fias Company, Philadelphia Electric Company, Delmarva Power and Light Company' and-Atlantic City Electric Company (the licensees) dated l March 23,.1989 and supplemental letters dated April 14, 1989, August 25, 1989, September 22, 1989 and October 26, 1989 complies i with the standards and requirements of the Atomic Energy Act of 1954, l as amended (the Act), and the Commission's rules and requlations set -forth in 10 CFR Chapter 11 i l B. The facility will operate in conformity with the aoolication, the l nrovisions.of the Act, and the rules and regulations of the 1 Commission; .C. There is reasonable assurance: (i) that the activities authorized by l this amendment can be conducted without endangering the health and safety of the public, and (iil that such activities will be conducted '1 in compliance with the Commission's regulations set forth in 10 CFR Chapter I; D. The issuance of this amendment will not be inimical to the common defense =and security or to the health and 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 chanaes to the Technical Specifica-tions as indicated in the attachment to this license amendment, and paragraph 2.C.(21 of Facility Operating License No. DPR-75 is herebv amended to read as follows: ..m. 2 m .si s- +s =
'e o -1, : r ef*9- ?F :. , i (2)' Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 82. are hereby incorporated in the license. The licensee.shall operate the facility in accordance with the Technical Specifications. 3. This license amendrent is effective as of its date of issuance and shall be implemented within 60 days of the date of issuance. FOR THE NUCLEAR REGULATORY COMMISSION '$ 0 v w Walter R. Butler, Director Project Directorate I-2 Division of Reactor Projects I/II
Attachment:
Changes-to the Technical Specifications-Date of Issu'ance: December 4, 1989 L i y I 1: -l u
9: 1 e
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~ ATTACHMENT TO LICENSE AMENDMENT NO. 82 FACILITY OPERATING LTCENSE NO. OPR-75 -POCKET NO. 50-31L L Revise Appendix A'as follows:- l-i l' Remove Pages Insert Paaes 3/4 B 3/4 8-16 j 3/4 8-17 3/4 8-17 3/4 8-18 3/4 8-18 1 3/4_8-19 l 1 3/4 8-20 3/4 8-21 3/4 8-22 3/4 8-23 l 3/4 8-24 3/4 8-25 i 3/4 8-26 3/4 8-27 4 B 3/4 8-1 8 3/4 8-1 B 3/4 8-2 B 3/4 8-2 i
rrreTRfCAL' POWER SiSTEMS i 3/4.813 EllCTRICAIJEOUIPMENT PROTECTIVE DEVICES CONTATNMENT PENETRATION CONDUCTOR OVERCL'RRENT PROTECTIVE DEVICES LIMTTINC CONDITION FOR OPERATION' 3.-8.3.1 All containment penetration conductor overcurrent protective devices required.. to provide thermal protection of penetrations sha* ' be OPERABLE. APPLICABILITY: MODES 1, 2, 3 and 4 ACTION: With one or more of the required containment penetration conductor overcurrent protective device (s) inoperable: l-l Restore the protective device (s) to OPERABLE status or de energize a. the circuit (s) by tripping either the primary or backup protective device, or racking out or removing the primary or backup device l ~ within' 72 hours, declare the affected system or component inoperable, and verify the primary or backup protective device to be 1 -tripped, or the primary or backup device racked out or removed at .least once per 7 days thereafter; the provisions of Specification { 1 3,0.4 are not applicable to overcurrent devices in circuits which l have their primary or backup protective device tripped, or which have the primary or backup device racked out or removed, or b. Be in at'least HOT STANDBY within the next 6 hours and in' COLD SHUTDOWN within the following 30 hours. I i - SURVEILIANCE REOUIREMENTS - I 4.8.3.1 All required containment penetration conductor overcurrent protective devices shall be demonstrated OPERABLE: [j a. At least once per 18 months: I 1. For at least one 4.16'KV reactor coolant pump circuit, such that all reactor coolant pump circuits 4re demonstrated-3 OPERABLE at least once per 72 months, by performance of: (a) A CHANNEL CALIBRATION of the associated protective relays, l' and L (b) An integrated system functional test which includes L simulated automatic actuation of the system and verifyin6 that each relay and associated circuit breakers and control circuits function as designed. l l l l SALEM UNIT 2 3/4 8-16 Amendment No. 82 L l 1
ELECTR? CAL PO'JER ' SYSTEMb' "'..... 9 SURVEILLANCE REOUIREMENTS /Continuedi 2. By verifying the OPERASILITY of the required molded case and lower voltage circuit breakers, by selecting and functionally . testing a representative. sample of at least 10% of all the circuit breakers of that type.. Circuit breakers selected for functional testing shall be selected.on a rotating basis. functional test shall consist of injecting a current The input at. the specified setpoint to each selected circuit breaker and verifying that each circuit breaker functions as designed. Circuit breakers found inoperable during functional testing shall be restorsd to OPERABLE status prior to resuming operation. For each circuit breaker found inoperable during least 10% of all the circuit breakers of the -inop shall also be functionally tested until no more failures are i found or all circuit breakers of that type have been-functionally tested. b. At least once per 60 conths by subjecting each circuit breaker to an inspection and preventive maintenance in accordance with procedures prepared in conjunction with its. manufacturer's recommendations. i ] v a v SALEM L' NIT 2 3/4 a.17 Amendment No.82
't ~ ;.- 7.. . TABLE 3.8 1 f .<a CONTAINMENT PENETRATION CONDUCT 0P, '{. OVERCURRENT PROTECTIVE DEVICSS I 'f \\ + l =l i. DELETED i i 2 i k i i SALE - WIT 2 3/4 8-18 Amendment No. 82
__ = _. - _ _ s - y. ~ 3/4. E' rfRTAICAL' POWER SYgg - : c m muts 3/4. 8.- 1 AND 3 /4. 8. 2 A 1,,jp,URCES AND ONSITE POWER DISTRIBUTION SYSTQg The OPERABILITY of the A.C. and D.C. power sources and associated distribution systems during operation ensures that sufficient. power will be available to supply the safety related equipment required for 1) the safe shutdown of the facil.ity, and 2) the mitigation and control of accident 3 ? conditions within the facility. The minimum specified independent and. redundant A.C. and D.C. power sources and distribution systems satisfy the requirements of Coneral Design Criterion 17 of Appendix "A" to 10 CFR Part 50. \\ The ACTION requirements'specified for the levels of degradation of the power sources provide restriction upon continued facility operation commensurate with the level of degradation. - The OPERABILITY of the power sources are consistent with the initial condition assumptions of the accident analyses and are based upon maintaining at least one redundant set of onsite A.C. and D.C. power sources and associated distribution systems OPERABLE-during accident conditions coincident with an assumed loss of offsite power and single failure'of the other onsite A.C. source. Th6 OPERABILITY of the minimum specified A.C. and D.C. power sources and associated distribution systems during shutdown and refueling ensures that 1) the facility can be maintained in the shutdown or refueling condition for extended time periods, and 2) sufficient instrumentation and control capebility is available for monitoring and maintaining the unit status. The Surveillance Requirements for demonstrating the OPERABILITY of the diesel generators is based upon the recommendations of Regulatory Guide 1.9, " Selection of Diesel Generator Set Capacity for Standby Power Supplies," March 10, 1971, and Guid2 1.108, "Feriodic Testing Diesel Generator Units Used as Onsite Electric Power Systems at Nuclear Power Plants," Revision 1, August 1977. 3/4.8.3' ELECTRICAL EOUIPMENT PROTECTIVE DEVICES Containment electrical penetrations and penetration conductors are ' protected by either doenergizing circuits not required during reactor operation or by demonstrating the OPERABILITY of primary and backup overcurrent protection circuit breakers during periodic surveillance. The surveillance frequency applicable to molded case circuit breakers and lower voltage circuit breakers provides assurance of breaker reliability by testing at least one representative sample of each manufacturer's brand of molded case and icwer voltage circuit breakers. Each manufacturer's molded case circuit breakers and lower voltage circuit breakers are grouped into representative samples which are then tested on a rotating basis to ensure that all breakers are tested. If a wide variety exists within any manufacturer's brand of molded case or lower voltage circuit breakers, it is necessary to further divide that manufacturer's breakers into groups and treat each group as a separate type of breaker for surveillance purposes. SALEM - UNIT 2 B 3/4 8 1 Amendment No.82
@1 ~ I* ELECTRICAL pO'.'ER SYSTEMS 1;" c, ^ RAEEE-/ Continued) A list of the' required contairaent penetration conductor overcurrent i protective de" ices, with information on location,' size and equipment powered by the pror e ;ive circuit is maintained in the UFSAR. The list is limited to ,L those over: rrent devices-installed for the purpose of keeping circuit fault current below the penetration racing. :It does not apply to other overcurrent devices 'which protect' penetrations where fault currents are less-than the sustained rating of the penetration. This is ' consistent with 'the requirements -of/IEEE 741 1986 which states that no special consideration is required'to protect electrical penetrations that can indefinitely withstand the maximum i fault current available. Setpoints are controlled by plant procedures and drawings and any-additions, deletions or modifications to the containment ~ penetration conductor overcurrent protective devices list is governed by section 50.59 of 10 CFR Part 50. i l 1 7 i l L SALEM UNIT 2 B 3/4 8 2 Amendment No. 82 l L -,,,, - -, - -,}}