ML20059J873
| ML20059J873 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 09/10/1990 |
| From: | Butler W Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20059J876 | List: |
| References | |
| NUDOCS 9009210011 | |
| Download: ML20059J873 (10) | |
Text
{{#Wiki_filter:. ' dne~og 9,, UNITED STATES' .[ n, NUCLEAR REGULATORY COMMISSION - . 5 WASHINGTON, D. C. 20065 y*...* J PUBLIC SERVICE ELECTRIC'& GAS COMP g' ' PHILADELPHIA: ELECTRIC COMPANY DELMARVA POWER AND LIGHT COMPANY: ATLANTIC CITY ELECTRIC COMPANY-DOCKET N0.~ 50-272 SALEM' GENERATING STATION. UNIT NO.' 1 4 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 114 -{ License No. DPR-70 4 1. The Nuclear Regulatory Comission:(the'Comission er.the NRC) has found that:. A. The application for amendment' filed by the Public Service 1 Electric & Gas Company, Philadelphia -Electric Company, Delmarva Power and. Light' Company and Atlantic City Electric Company (the licensees) dated May 21,1990 and supplemented by letter dated July 18, 1990, complies-with the standards and requiremen:ts of the Atomic Energy Act of'1954, as amended (the Act) and the Connission's rules and. regulations set i forth in 10 CFR Chapter I; j i =! n B. The facility will operate in conformity with.the application, the~' i i provisions of the Act, and the? rules and regulations of the Commission; i 'i 1 C. There is reasonable assurance: (i)thatthe: activities-authorizedby-this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted i in compliance with the Commission's regulations set forth:in ~10 CFR Chapter I; 1 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 Connission's regulations and all. applicable requirements have been' satisfied. 2. Accordingly, the license is amended by changes to theLTechnical Specifica-t tions as indicated in the attachment to this license amendment, and7 paragraph 2.C.(2) of Facility Operating License No.:DPR-70 is hereby amended to read as follows: ir 1 9009210011 900910 {DR ADOCK0500g2 S s
i . f -- t (2) Technical Specifications and Environmental Protection Plan: The Technical Specifications contained in Appendices A and B, as - i revised through Amendment No.114, are hereby incorporated in the license. The licensee shall operate the facility,in accordance with~ the Technical Specifications. 3. This license amendment is effective as of its date of issuance and shall be implemented within 60 days of othe ~date of issuance. 6 FOR THE NUCLEAR REGULATORY COMMISSION /S/i i Walter R; Butler, Director-Project Directorate 1-2 Division of Reactor Projects-1/Il-
Attachment:
4 Changes to the Technical Specifications t Date of Issuance: September 10, 1990 ,a -j - ) L-l u-i i i-pY Y A-PDI-2/PM G PDI-2/ W///4#/ WButler p en JStone:mj g /90 Q /90 7 /f9/90 /10/90 i 1
ne: 2., (2); Technical-Specifications and Environmental. Protection. Plan = The Technical-Specifications contained in Appendices A'and 8, as'. revised through Amendment No. - 114, are hereby incorporated in the . license.: The. licensee shall operate the' facility.in accordance with the Technical Specifications. 3, This iicense amendment 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 [ Walter R.' Butler, Director Project Directorate I-2 Division-of Reactor Projects I/II
Attachment:
Changes to the Technical Specifications Date of Issuance: ' september 10, 1990 -j f ) ( t L l, z s I
-( ATTACWNENT.TO. LICENSE.ANENDNENT.NO. 114-. FACILITY.0PERATING LICENSE.N0..DPR, DOCKET NO,;50 272 Revise Appendix A as follows: Remove.Page-Insert Page 3/4 3 -3/4 3-5 i h k i .I i I , Li -- wi L. - --. -------. A.-- ------------.
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l TABLE 3.3 1-(ContinuedI TABLE NOTATION .With the reactor trip _ system breakers in the c1 m position and the; control rod drive system capable _of-rod' withdraw i. The channel (s). associated with the-protective functions derived from. the out of service Reactor-Coolant Loop shall be placed in the tripped condition.- The_ provisions of_ Specification 3;0.4 are not applicable.- High voltage to detector may be de energized above P 6. If ACTION Statement 1 is entered as a result of Reactor Trip Breaker ~ e*# (RTB) or Reactor Trip-Bypass Breakers (RTBB) maintenance testing results exceeding:.the following acceptance criteria, NRC reporting shall be'made j in accordance with Specification 6.9.1.9:' i
- 1. A RTB or RTBB trip failure during any surveillance test with itas than or equal ~to 300 grams of weight added to the breaker. trip-bar.
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- 2. A RTB or RTBB time response failure that results in the overall' reactor trip system time response exceeding the Technical ~
Specification limit. ACTION STATEMENTS ACTION 1 - With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement,-be_in HOT STANDBY within 6 hours; however,'one channel may be bypassed-.for up to 1 2 hours for surveillance-testing per Specification' 4.1.1.1 j provided the other channel is OPERABLE. i ACTION 2 - With the number of OPERABLE channels one.less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the following conditions are satisfied; The inoperable channel is placed in the. tripped 1 a. condition within 1 hour. b. The Minimum Channels OPERABLE requirement is met; ~ however, one additional channel may be' bypassed for up to i 2 hours for surveillance testing per Specification ~ l 4.3.1.1.. I Either, THERMAL POWER is restricted to f 75% of-RATED c. l THERMAL and the Power Range, Neutron Flux trip setpoint I is reduced to f 85%'of RATED THERMAL. POWER within 4 hours; 1 or, the QUADRANT POWER TILT RATIO is monitored at least i once per 12 hours'.
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,u ACTION 3 - With the number of channels-OPERABLE one less than required by the Minimum Channels OPERABLE requirement and with the 4 THERMAL POWER level: 4H o SALEM - UNIT 1 3/4 3-5 Amendment No. 114 F4 m =
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.....) e L PUBLIC SERVICE ELECTRIC & GAS COMPANY. L PHILADELPHIA' ELECTRIC COMPANY l DELMARVA POWER AND LIGHT COMPANY l ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-311-SALEM GENERATING STATION. UNIT NO. 2 AMENDMENT'TO FACILITY-OPERATING LICENSE Amendment No. 96= License No. DPR-75 5 1. The Nuclear Regulatory Comission.'(the Comission or the NRC) has found_ that: A.. The application for amendment filed by,the Public Service Electric & Gas Company, Philadelphia' Electric Company,(Delmarva Power and L Company and Atlantic City Electric Company thelicensees) dated a May 21, 1990 and supplemented by letter dated July 18, 1990,-complies-with the standards and requirements of the Atomic Energy Act of 1954, 4 as amended (the Act), and the Comission's rules and regulations set . 7 forth in 10 CFR Chapter I;-- B. The facility will operate in conformity with the application, the: provisions of the Act, and the rules'anJ regulations of the Comission; C. There is reasonable assurance:-(i) that-the activities authorized by { this amendment can be conducted without endan ering the health and safety of the public, and-(.ii) that such acti ities will be conducted-in compliance with the Comission'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-I the Comission's regulations-and all app 11 cable requirements;have been satisfied. >2. Accordingly, the license is amended by changes to the Technical Specifica-tions as indicated in the attachment to this~ license amendment,.and paragraph 2.C.(2) of Facility Operating License No. DPR-75 is hereby amended to read as follows: f - i----- -..---.- ,,.-4 + et
n 4 .b .2.- l(2)"TechnicalSpecificationsandEnvironmentalProtectionPlan L The' Techdical Specifications contained in Appendices A and B, as e revised through Amendment No. 96 -, are herebyiincorporated in the _ . license. The licensee shall operate the facility in accordance.with the Technical-Specificctions. ~ ~ 3. This license amendment.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 /S/' J Y Walter R. Buti n,'Directorf Project Directcrate I-2 Division of Reactcc Projects I/II'
Attachment:
Changes to the Technical-u Specifications 1 Date;of Issuance: September'10,19905 i j pa 29' \\ ')
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(2) Technical Specifications ~and Environmental Protection Plan The Technical Specifications ~ contained;in Appendices A.and B, as revised through-Amendment No. 96, are.hereby incorporated in the in license. The licensee shall operate lthe facility in a:cordance with the Technical Specifications. i i 3. This license amendment is effectiva as of its date of issuance'and shall .l be implemented'within 60 days of the date of issuance. i-FOR THE NUCLEAR REGULATORY. COMMISSION- -Walter R. Butler, Director Project Directorate-I.2 Division of Reactor Projects I/II Attachment-Changes to the Technical Specifications Date of Issuance: -Septen.ber 10, 1990 e -) 's i A l -I l 1 1 t I L i l l'
ATTACWMENT.TO. LICENSE. ANENDNENT. N0. 96 FACILITY.0PERATING. LICENSE.NO,.DPR-75' DOCKET.NO. 50-311 l: L Revise Appendix A as follows: 1 RemoveL age Insert.Page P 3/4 3-5 3/4:3-5 1 i l l-c f I L ~
m-t r ~ ( Co..cinued ) TABLE 3.3-1 ) 'l TABLE NOTATION 4 1.: With the reactor trip system breakers in the ciceed position and the 3 control rod drive syste.n capable of rod withdrawal.- The channel (s) associated with the protective functions derived from the out of service Reactor Coolant. Loop shall be placed in the tripped ~ condition. ~ The provisions of specification 3.0.4 are not applicable. High voltage to detector may be de-energized above P-6.
- If ACTION Statement 1 is entered as a result of Reactor Trip Breaker:
t (RTB) or Reactor Trip B3 pass Breaker (RTBB) maintenance testing redults exceeding the following acceptance criteria, Nnc reporting shall be made'in ,t accordance with specification 6.9.1.9: 1. A RTB or RTBB trip failure during any surveillance test with less than or equal to 300 grams of weight =added to the breaker trip bar. t 2. A RTB or RTBB time response failure that results in the - 3 overall reactor trip system time response exceeding =the Technical specification limit. ACTION STATEMENTS t ACTION 1 With the number of channels OPERABLE'one lide than required _ .) ay the Minimum Channels OPERABLE requirement,'be in HOT STANDBY within 6 hours; however, one channel may be' bypassed for up to.2 hours for surveillance testing per specification 4.3.1.1 provided the other channel is OPERABLE. ACTION 2 With the number of-OPERABLE: channels one.less thP.n the Total Number of Channels, STARTUP.and/or POWER OPERATION may proceed provided the following conditions are satisfied l -i The inoperable channel is placed Jyt the tripped condition' a. within 1 hour. O b. The Minimum Channels OPERABLE requirement is metschowever,. one additional channel may be bypassed for up,to-2 hoursifor j ~ surveillance testing per specification 4.3.1.1. l Either, THERMAL POWER is restricted to f 75% of TTTED THERMAL c. and the Power Range, Neutron Flux trip setpoint is reduced'to $ 854 of RATED THERMAL POWER within 4 hours; or, the QUADRANT POWER TILT RATIO is monitored at least once per 12-hours. d. The QUADRANT POWER TILT RATIO, as indicated by the-remaining-three detectors, is verified consistant with the norma.ized symmetric power distribution obtained by veing the movable in-core detectors in the four pairs of symmetric thimble locations at least once per 12 hours when THERMAL POWER is greater than 75% of RATED THERMAL POWER. L SALLM UNIT 2 3/4 3-5 Amendment No. 96 l I .}}