ML20082C285
| ML20082C285 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 07/01/1991 |
| From: | Butler W Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20082C287 | List: |
| References | |
| NUDOCS 9107180269 | |
| Download: ML20082C285 (13) | |
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UNITED STATES r7 i
NUCLEAR REGULATORY COMMISSION
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WASHINGTON. D.C. 20065
%,.'.s,,...f PUBLIC SERy!CE ELECTRI,C,,&,G,AS,COMPA!iY PHILADELPHI A ELECTRIC COMPAtlY DELMARVA, POWER At!D Liji!IT_C0!1,PAtQ ATLANTIC CITY ELECTRIC C011PANY DOCKET tl0. 50-?7,2 SALEM flUCLEAR GENERATit:G STAT 10ft,"JNIT NO. 1 Af'E t:CliE f fT,,Tp,,F AC l l l T Y, 9,P E R ATJ !1MJ C E!1 S E Amendment flo.127 License No. DPR-70 1.
The fluclear Regulatory Commissien (the Commission or the NRC) has found that:
A.
The applications for amendment filed by the Public Service Electric &
Gas Company, Philadelphia Electric Company, Delmarva Power and Light Company and Atlantic City Electric Company (the licensees) both dated April 3, 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 cor.formity 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 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 amendnent 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 Specifica-tions as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License flo. DPR-70 is hereby amended to read as follows:
9107100269 910701 PDR ADOCK 05000272 P
~ (2) Technj,ca,1 Specifications and Environmental Protection Plan The Technical Specifications contained in Appendices A and B, as revised through Amendment No.127, 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 the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION f /(24 ts Walter R. Butler, Director Project Directorate I-2 Div'sion of Reactor Projects - 1/11
Attachment:
Changes to the Technical Specifications Date of Issuance: July 1, 1991 I
4 ATTACHMENT TO LICENSE AMEN 0 MENT NO.127 FACILITY OPERATit;G LICENSE NO. OPR-70 DOCKET NO. 50..27_2 Fevise Appendix A as follows:
Remove Page Insert Page 3/4 10-2 3/4 10-2
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l SPECIAL TEST EXCEPTIONS GROUP HEIGHT, INSERTION AND POWER DISTRIBUTION LIMITS LIMITING CONDITION FOR OPERATION
.. 22S53333333333E.33E23 3 33E3 22E2E33333333333335. 38 33333 333335233333 235 3.10.2 The group height, insertion and power distribution limits of Specifications 3.1.3.1, 3.1.3.4, 3.1.3.5, 3.2.1, and 3.2.4 may be suspended during the performance of PHYSICS TESTS provided:
a.
The THERMAL POWER is maintained s 85% of d'TED THERMAL POWER, and b.
The limits of Specifications 3.2.2 and 3.2.3 are maintained and determined at the frequencies specified in Specification 4.10.2.2 below.
APPLICABILITY: MODE 1 ACTION:
With any of the limits of Specifications 3.2.2 or 3.2.3 being exceeded while the requirements of Specifications 3.1.3.1, 3.1.3.4, 3.1.3.5, 3.2.1 and 3.2.4 are suspended, either:
a.
Reduce THERMAL POWER sufficient to satisfy the ACTION requirements of Specifications 3.2.2 and 3.2.3, or b.
Be in HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
SURVEILLANCE REQUIREMENTS 4.10.2.1 The THERMAL POWER shall be determined to be s 85% of RATED THERMAL POWER at least once per hour during PHYSICS TESTS.
4.10.2.2 The below listed surveillance requirements shall be performed at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> during PHYSICS TESTS:
a.
Surveillances 4.2.2.2 and 4.2.2.3.
b.
Surveillances 4.2.3.1 and 4.2.3.2.
SALEM - UNIT 1 3/4 10-2 Amendment No.127
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UNITED STATES n
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NUCLEAR REGULATORY COMMISSION 5a'
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PUBLIC SERJlCE, ELECTR1,C, &, GAS,COM, pat!Y PHILADELPHIA ELECTRIC COMPANY DElliARVA P0p,ER, At:DJ,1GH,T, COM,PAtq ATLANTIC CITY ELECTRIC COMPANY DOCKEi p,0,, 50-311 SALEM NUCLEAR GENERATING SLAT!ON UtilT N3._2 x
AMENDMENT TO FACILITY Oi>ERAii2 LICENSE Amendment No. 106
'icense No. DPR-75 1.
The Nuclear Regulatory Conmission (the Commission or the NRC) has found that:
A.
The applications for amendment filed by the Putlic. Service Electric &
Gas Company, Philadelphia Electric Company, Delmarva Power and Light Company and Atlantic City Electric Company (the licensees) both dated April 3, 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; E.
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 set forth in 10 CFR Chapter 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 Commission's regulations and all applicable 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:
(2) Technical Specifj,ca,tjpns, an,d,En,vj,rpnm,en,ta_1, Protection Plan The Technical Specifications contained in Appendices A and B, as revised through Amendment ?!o.106. 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 the date of issuance.
FOR THE ttVCLEAR REGULATORY COPNISS10tl M 2-c 6
Walter R. Butler, Director Project Directorate 1-2 Division of Reactor Projects - 1/11
Attachment:
Changes to the Technical Specifications Date of Issuance: July 1, 1991 -
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i ATTACHMENTTOLICENSEAMEf1D[1Efq_NO._yJ)L,.
FACILITY OPERATING LICENSE-NO. DPR-75 DOCKET fl0. 50-311-Revise Appendix A as follows:
- Remove Pages Insert Pages 3/4 2-17 3/4 2-17 3/4 3-40 3/4 3 3/4 4-17 3/4 4-17 3/4 4-18 3/4 4-18 3/4 4-19 3/4 4-19 3/4 10-?
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TABLE 3.2-1 DNB PARAMETERS PARAMETER LIMITS 4 Loops in Operation Reactor Coolant System T,yg 1 582*r Pressurizer Pressure 1 2220 psia l
I Reactor Coolant System 1 357200 gpm Limit not applicable during either a THERMAL POWER ramp in excess of
$% RATED THERMAL P0kER per minute or a THERMAL POWER step in excess of 10% RATED THERMAL POWER.
8 Includes a 2.2% flow uncertainty plus a 0.1% measurement uncertainty due to feedwater venturi fouling.
SALEM - UNIT 2 3/4 2-17 Amendment No.106 j'
1 TABhE 3.3-6 (Continued)
TABLE NOTATION
-ACTION 23 -
With the number of channels OPERABLE less than required' by the Minimum Channels OPERABLE requirement, perform area surveyslof the monitored-area with' portable monitoring instrumentation at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />..
ACTION 24 -
With the number of channels OPERABLE less than required by the' Minimum _ Channels OPERABLE requirement, comply with
_the_ ACTION, requirements of Specification 3.4.7.1.
l ACTION 25 -
With~the number.of channels OPERABLE less than required by the Miniaua Channels OPERABLE requirement, comply with~
the ACTION. requirements of Specification 3.0.9.
. ACTION 26 -
_-Vith the number of OPERABLE-Channels less than required by the Minimum Channels OPERABLE requirements, initiate-the preplanned alternate method of_ monitoring the appropriate parameter (s), within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />,'and:
1)
_eitherirestore_the. inoperable Channel (s)-to-OPERABLE status within 7 days of the event, or 2) prepare and submit a Special Report-to the Commission pursuant to Specification 6.9.2 within 14 days following the event outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the system to OPERABLE status.
1.-
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' SALEM - TWIT 2 3/4 3-40 Amendment No.106 l
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e REACTOR COOLANT SYSTEM OPERATIONAL LEAKAGE LIMITING CONDITION FOR OPERATION
==========================================================..............
3.4.7.2 Reactor Coolant System leakage shall be limited to:
a.
No PRESSURE BOUNDARY LEAKAGE, b.
1 GPM UNIDENTIFIED LEAKAGE, 1 GPM total primary-to-secondary leakage through all steam c.
generators and 500 gallons par day through any one steam generator, d.
10 GPM IDENTIFIED LEAKAGE from the Reactor Coolant System, and 40 GPM CONTROLLED LEAKAGE at a Reactor Coolant System pressure e.
of 2230 20 psig.
f.
1 GPM leakoge at a Reactor Coolant System pressure of 2230 1 20 psig from any Reactor Coolant System Pressure Isolation Valve specified in Table 3.4-1.
APPLICABILITY: MODES 1, 2, 3 and 4 ACTION:
a.
With any PRESSURE BOUNDARY LEAKAGE. be in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />, b.
k'ith any Reactor Coolant System leakage greater than any one of the above limits, excluding PRESSURE BOUNDARY LEAKAGE and leakage from Reactor Coolant System Pressure Isolation Valves, reduce the leakage rate to within limits within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or be in at least HOT STANDBY within the nex' 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
With any Reactor Coolant System Pressure Isolation Valve leakage c.
l greater than the above limit, isolate the high pressure portion of the affected system from the low pressure portion within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by use of at least two closed manual or deactivated automatic valves, or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and l
in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE REQUIREMENTS
==================================================================
4.4.7.2.1 Reactor Coolant System leakages shall be demonstrated to be l
within each of the above limits by; a.
Monitoring the containment atmosphere particulate radioactivity monitor at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, b.
Monitoring the containment sump inventory at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
SALEM - UNIT 2 3/4 4-17 Amendment No.106 l
a REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued)
BBBEGEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEE=EEEEEEEEEEEEEEEEEEEEEEEEEEEEE c.
Measurement of the CONTROLLED LEAKAGE from the reactor coolant pump seals at least once per 31 days when the Reactor Coolant System pressure is 2230 2 20 psig and valve 2CV71 is fully closed, d.
-Performance of a Reactor Coolant System water inventory balance at least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. The water inventory balance shall be performed with the plant at steady state conditions. The provisions of specification 4.0.4 are not applicable for entry into Mode 4, and Monitoring the reactor head flange leakoff system at least once e.
per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
4.4.7.2.2 Each Reactor Coolant System Pressure Isolation Valve specified in l
Table 3.4-1 shall be demonstrated OPERABLE pursuant to Specification 4.0.5, except that in lieu of any leakage testing required by Specification 4.0.5, each valve shall be demonstrated OPERABLE by verifying leakage to be within its limit:
a.
At least once per 18 months.
b.
Prior to entering MODE 2 whenever the plant has been in COLD SHUTDOWN for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or more and if leakage testing has not been performed in the previous 9 months.
c.
Prior to returning the valve to service following maintenance repair or replacement work on the valve.
d.
For the Residual Heat Removal and Safety Injection Systems hot and cold leg injection valves and accumulator valves listed in Table 3.4-1 the testing will be done within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> following valve actuation due to automatic or manual action or flow through the valve. For all other systems testing will be done once per refueling.
The provisions of specification 4.0.4 are not applicable for entry into MODE 3 or 4.
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SALEM - UNIT 2 3/4 4-18 Amendment No. 106
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REACTOR COOLANT SYSTEM TABLE 3.4-1 REACTOR COOLANT SYSTEH PRESSURE ISOLATION VALVES VALVE NO FUNCTION 21SJ43 Safety Injection (L.P. from RHR Pumps to Cold Legs)
- 22SJ43-Safety Injection (L.P. from RHR-Pumps to Cold Legs) 23SJ43 Safety Injection (L.P. from RER Pumps to Cold Legs) 24SJ43 Safety Injection (L.P. from RHR Pumps to Cold Legs) 21SJ55 Safety Injection (Accumulator Discharge to Cold Legs) 22SJ55 Safety Injection-(Accumulator Discharge to Cold Legsl 23SJ55 Saf ety Injection (Accumulator Discharge to Cold Legsl 24SJ55 Safety Injection (Accumulator Discharge to Cold Legs) 21SJ56 Safety Injection (Accumulator Discharge to Cold Legs) 22SJ56 Safety Injection (Accumulator Discharge to Cold Legs) 23SJ56 Safety Injection (Accumulator Discharge to cold Legs!
24SJ56 Safety Injection (Accunulator Discharge to Cold Legs) 21SJ17-Safety Injection (Boron Injection to Cold Legs) 22SJ17 Safety Injection (Boron Injection to Cold Legs) 23SJ17 Safety Injection (Boron Injection-to Cold Legs)
-24SJJ7 Safety Injection (Boron Injection to Cold Legs) 2SJ150 Safety Injection =(Boron Injection to cold Legs) 21SJ139 Safety Injection (H.P. from SI Pumps to Hot Legs l 22SJ139 Safety Injection-(H.P. from SI Pumps to Hot Legs) 23SJ139 Safety Injection (H.P. from SI Pumps to Hot Legs) 24SJ139 Safety-Injection (H.P. from SI Pumps to Hot Legs) 21SJ156 Safety Injection (H.P. from SI Pumps to Hot Legsl 22SJ156 Safety Injection-(H.P. from SI Pumps to Hot Legs) 23SJ156 Safety Injection (H.P. from-SI Pumps to Hot Legs) 24SJ156 Safety Injection (H.P.-from SI Pumps to Hot Legs) 21SJ144 Safety Injection (H.P. from SI Pumps to. cold Legs) l-22SJ144_
Safety Injection (H.P. from SI Pumps to Cold Legs) 1.
23SJ144 Safety Injection (H.P. from SI Pumps to Cold Legs)
I 24SJ144-Safety Injection (H.P. from SI Pumps to Cold Legs) l
,2RH1 RHR Suction from Hot Leg No. 21
- 2RH2.
RHR Suction from Hot Leg No. 21 23RH27 RHR Discharge-to not Leg No. 23 1
24RH27 RHR Discharge to Hot Leg No. 24 SALEM'- UNIT 2 3/4 4-19 Amendment No.106
SPECIAL TEST EXCEPTIONS GROUP HEIGHT, INSERTION AND POWER DISTRIBUTION LIMITS LIMITING CONDITION FOR OPERATION
=====================..=================================.....................
3.10.2 The group height, insertion and power distribution limits of Specifications 3.1.3.1, 3.1.3.4, 3.1.3.5, 3.2.1, and 3.2.4 may be suspended during the performance of PHYSICS TESTS provided:
I a.
The THERMAL POWER is maintained less than or equal to 85% of RATED THERMAL POWER, and b.
The limits of Specifications 3.2.2 and 3.2.3 are maintained and determined at the frequencies specified in Specification 4.10.2.2 below.
APPLICABILITY: MODE 1.
ACTION:
Vith any of the limits of Specifications 3.2.2 or 3.2.3 being exceeded while the requirements of Specifications 3.1.3.1, 3.1.3.4, 3.1.3.5, 3.2.1 and 3.2.4 are suspended, either:
a.
Reduce THERMAL POWER sufficient to satisfy the ACTION requirements of Specifications 3.2.2 and 3.2.3, or b.
Be in HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
SURVEILLANCE REQUIREMENTS S333E353553522333333333333333E333E33.EE3333333333R33333333333B333333EEE3533333 4.10.2.1 The THERMAL POWER shall be determined to be less than or equal to 85% of RATED THERMAL POWER at least once per hour during PHYSICS TESTS.
4.10.2.2 The below listed surveillance requirements shall be performed at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> during PHYSICS TESTS:
a.
Surveillances 4.2.2.2 and 4.2.2.3.
b.
Surveillances 4.2.3.1 and 4.2.3.2.
I See page 3/4 10-3 SALEM - UNIT 2 3/4 10-2 Amendment No. 106 i
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