ML20012E977

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Amends 153 & 154 to Licenses DPR-44 & DPR-56,respectively, Decreasing Required Calibr Frequency for Reactor Water Level & Reactor Pressure Surveillance Instrumentation Specified in Tech Spec Table 4.2.F
ML20012E977
Person / Time
Site: Peach Bottom  Constellation icon.png
Issue date: 03/27/1990
From: Butler W
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20012E978 List:
References
NUDOCS 9004090216
Download: ML20012E977 (10)
v • d • e


Text

{{#Wiki_filter:. i. i ~ .f ^ 'c, UNITE D sTAf ts E '1 NUCLE AR REGULATORY COMMISSION r l i uswiwovow, p. c. 9666 4 h,..v i l PHILADELPHIA CLECTRIC COMPANY Pl4 1C 5';RVICT ELI61RT0 AND 5A5 COMPANY JELMA (VA POWIR AND (15M1 C(mrAMT i ATLANTIC CITT ELECTRIC CterAWT I f DOCKET NO. 50 ?77 PEACH BOTTOM ATOMIC POW [R STATION, l' NIT NO. 2 [ AMENDMENT TO FAC1(1TY OPERATING LICENSE Amendment No. 153 l License No. DPR-44 i 1. The Nuclear Regulatory Comission (the Comission) has found that: i t A. The application for amendment by Philadelphia Electric Corpany, et l al.(thelicensee)datedJuly 12, 1989, complies with the standards 1 and requirements of the Atomic Energy Act of 1954, as amended (the ? Act), and the Comission'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 Comission; j i l 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 Comission's regulations; f D. The issuance of this amendment will not be inimical to the comon 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 i the Comission's regulations and all applicable requirements have been l 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: t f 9004090216 900327 PDR ADOCK 05000277 P PDC u

y y ( ,i, o L i. (2) Technical Specifications 7 The Technical Specifications contained in Appendices A and C as revised through Anendment No.153, are hereby incorporated In the i license. PECO shall operate the facility in accordance with the Technical Specifications. 3. This license anendment is effective as of its date of issuance. FOR THE NUCLEAR REGULATORY COMMIS$10N /s/ Walter R. Butler, Director Project Directorate 1-2 Division of Reactor Projects 1/11 Attachsent: Changes to the Technical Specifications Date of Issuance: March 27, 1990 i i l i i l A PDI-2/PM n OGC t8 PDI-2/D / GSuh:mjf)d' l B' WButler LN I n 2 / cf f 90 S /11/90 \\ b 8/ 90 0 e

t i (2) Technical Specifications I i The Technical Specifications contained in Appendices A and B as revised through Amendment No.153, are hereby incorporated In the

license, PECO shall operate the facility in accordance with the Technical $pecifications, 3.

This license amendnent is effective as of its date of issuance, I FOR THE NUCLEAR REGULATORY COMMIS$10N ft (E f u-v Walter R. Butler, Director Project Directorate 1 2 Division of Reactor Projects 1/11 { Attachrent' Changes to the Technical e Specifications Date of Issuance: March 27, 1990 i i ? [ t f I i i i 5 't

jt e ATTACHMENT TO LICENSE AMENDMENT NO.153 i FACILITY OPERATING LICENSE NO. DPR-44 f t DOCKET NO. 50 277 i Replace the following page of the Appendix A Technical Specifications with l the enclosed page. The revised areas are indicated by marginal lines. ( Remove Insert 86 86 c l

-3 UNIT 2 TABLE 4.2.F k MINIMUM TEST AND CALIBRATION FREQUENCY FOR SURVEILLANCE INSTRUENTATION ag Instrument Channel Calibration Fr s.-{y Instrument Check f 1) Reactor W ter level (narrow range) Once/ operating cycle Once Each Shift l {y 2) Reactor Wter level (wide range) Once/ operating cycle Once/def k 3) Reactor Wter Level (fuel zone) Once/ operating cycle Once/ day y 4) Reactor Pressure Once/ operating cycle Once Each Shift l S) Drywell Pressure Once/6 sonths Once Each Shift

6) Wide Range Drywell Pressure Once/ operating cycle Once/ day
7) Subatmospheric Drywell Pressure Once/ operating cycle Once/ day E
8) Drywell Teaperature Once/6 months Once Each Shift i
9) Suppression Chamber W ter Temperature Once/ operating cycle Once Each Day i
10) Suppression Chamber W ter Level Once/6 months Once Each Shift
11) Wide Range Suppression Chamber Once/ operating cycle Once/ day Water level
12) Control Rod Position N/A Once Each Shift 4
13) Neutron Monitoring (APRM)

Twice Per week Once Each Shift

14) Safety /Reliel Valve Position Once/ operating cycle Cace/ month Indicator (acoustics)
15) Safety / Relief Valve Position N/A*

Once/ month Indicator (thermocouple)

16) Safety Valve Position Todicator Once/ operating cycle Once/ month (acoustics)
17) Safety Valve Position Indicator N/A*

Once/ month (thermocouple) _ _.... _ _ _ _, _ _ _ _ _, - _ _.. _ _. _ _. ~.., _ _ _ _ _ _. _, _ _ _. _.. _. _ _. _. ~ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _. - _. _... _ _. _. -., _ _ _.. _.

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{ wAsmwotow.o.c 30666 \\,...../ PHILADE;PHIA ELCCTFIC COMPANY PUB;10 KRv KI Ucruc up 6% cpMPANY gnMA1VA POW R AND L' 5M UUMPANT ATLANTIC CITY [CTH10 CUmVANT DOCKET NO. 50-?78 PEACH BOTTOM ATOMIC 00WER STATION. UNIT NO. 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 154 License No. DPR.56 1. The Nuclear Regulatory Comission (the Comission) has found that: A. The application for amendment by Philadelphia Electric Company, et al. (the licensee) dated July 12, 1989, complies with the standards and requirements ei the Atomic Energy Act of 1954, as amended (the Act), and the Comission'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 regulatiens of the Comissiont C. There is reasonable assurance (i) that the activities authori:ed 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 Comission's regulationst D. The issuance of this emendment will not be inimical to the comon defense and security or to the health or safety of the publict and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission'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 racility Operating License No. DPR 56 is hereby amended to read as follows: 1

F I 2 1 (2) Technical Specifications The Technical Specifications contained in Appendices A and B as f i' revised through Anendment No.154 are hereby incorporated in the license. PECO shall operate the f actitty in accordance with the Technical Specifications. I f 3. this license amendment is effeed ve as of its date of issuance. F0h THE NUCLEAR REGULATORY COMMISSION /s/ Walter R. Butler Director Project Directorate 1-2 Division of Reactor Projects 1/11 l Attachnent: Changes to the Technical Specifications Date of issuance: March 27, 1990 i l' s C i I g. l i [ If A PDI-2/PM o OGC PDI-2/Dl Mt n GSuh:mj dM KButler h l i /S0 2 / 9 /90 0 o /l /90 /90

~ o 2 (2) Technical $pecifications The Technical Specifications contained in Appendices A and B, as l revised through Amendment No.154 are hereby incorporated in the i license. PECOshalloperatetheIacilityinaccordancewiththe Technical Specifications. l 3. This license amendment is effective as of its date of issuance, f FOR THE NUCLEAR REGULATORY COMMIS$10N ki$ v U Walter R. Futler, Director Project Directorate 1-2 r Division of Reactor Projects 1/11 I i Attachment Changes to the Technical $pecifications i Date of Issuance March 27, 1990 I I i i i i I t h I I I

F ATTACHMENT TO LICENSE AMENDMENT NO. 154 i. i l i I TAtlLITY OPERATING LICENSE NO. DPR.$6 DOCKET NO. 50 278 Replace the fo110 win!1 page of the Appendix A Technical Specifications with i the enclosed page. "he revised areas are indicated by marginal lines. Remove Insert i 86 86 t t i e 1 k f i I t i i I { l 5 t f i l

t UNIT 3 TABLE 4.2.F $g MINIMUM TEST AND CALIBRATION FREQUENCY FOR SURVEILLANCE INSTRUMENTATION ~ 8 Instrument Channel Calibration Fr v r.cy Instrument Check s ~E 1) Reactor Water Level (narrow ranga) Once/ operating cycle Once Each Shift l ~ g y 2) Reactor Water Level (wide range) Once/ operating cycle Once/dey y 3) Reactor Water Level (fuel zone) Once/ operating cycle Orre/ day y 4) Reactor Pressure Once/ operating cycle Once Each Shift l ~ 5) Drywell Pressure Once/6 months Once Each Shift

6) Wide Range Drywell Pressure Once/ operating cycle Once/ day
7) Subatmospheric Drywell Pressure Once/ operating cycle Once/ day E

' 8) Drywell Temperature Once/6 months once Each Shift

9) Suppression Cham 6er Water Temperature Once/ operating cycle Once Each Day
10) Suppression Chamber Water Level Once/6 months Once Each Shift
11) Wide Range Suppression Chamber Once/ operating cycle Once/ day Water Level
12) Control Rod Position N/A Once Each shift
13) Neutron Monitoring (APRM)

Twice Per Week Once Each Shift

14) Safety / Relief Valve Position Once/ operating cycle Once/morth Indicator (acoustics)
15) Safety / Relief Valve Position N/A*

Once/munth Indicator (thermocouple)

16) Safety Valve Position Indicator Once/ operating cycle Once/ month (acoustics)
17) Safety Valve Position Indicator N/A*

Once/ month (themocouple) . _ _ _ _. _ _ _ _... _.. _ _.,. - -. _. _ ~.. _ _ _ _. - _ _.. _ _,.. -. _, -. _ _. _ _ _ _ _. _ _ _ _. _ _ _ _... _ _ _ - _ _ _ _. _}}

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