ML20085B511
| ML20085B511 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 07/30/1991 |
| From: | Capra R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20085B512 | List: |
| References | |
| NUDOCS 9108020125 | |
| Download: ML20085B511 (9) | |
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3-i UNITED STATES i
NUCLEAR REGULATORY COMMISSION o
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BALTIMORE GAS AND ELECTRIC COPPANY DOCKET NO. 50-317 C AL VERT CLJff,$, tJp,C,LJ AR, Pp,Wf,R, PL,Ap,T, pp,1,T, pp,.J AMENpMEp,T,,1p,,FKILITY OPERA,TJpG LICENSE Amendment flo.157 License No. DPR-53 1.
The t;uclear Regulatory Commission (the Commission) nas found that:
A.
The application for amendment by Baltimore Gas and Electric Company (thelicensee)datedMay 24, 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 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 Specifications as indicated in the attachment to this license auendment, and paragraph 2.C.(?) of Facility Operating License No. DPR-53 is hereby amended to read as follows:
9108020125.910730 PDR ADOCK 050 7
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2 (T) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment !!o.157, are hereby incorporated in the license. The licensee shall operate the f acility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance and shall be implemented within 30 days.
FOR THE tiUCLEAR REGULATORY C0!' MISSION
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[ P.obert A. Capra, Director Project Directorate 1 1 Division of Reactor Projects. 1/11 Office of tiuclear Reactor Regulation Attachnent:
Changes to the Technical Specifications Date of Issuance:
July 30,1991
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/ 'n UNITED STATES
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i NUCLEAR REGULATORY COMMISSION i
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l B AL T I MO R E G A.S..A.t4.D..E.L.E.C.T.R.I C COMP ANY l
DOCKET N0_. 50-318 C ALVERT_CLjff 5, Np,CLE,AR, f 0,WE,R, f,L,At1,T,, pp1,T, fl.0,, 2 AMEl$ melit T0 FACILJTY_ OPERA,TJt4_G LICEllSE Amendment flo.137 License lio. DPR-69 1.
The fluclear Regulatory Consnission (the Commission) has found that:
A.
The application for amendment by Baltimore Gas and Electric Company (the licensee) dated May 24, 1991, complies with the standards and requiren,ents 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 reguhtions 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 defanse 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 Specifications as indicated in the attachment to this license r
I amendment, and paragraph 2.C.2 of Facility Operating License flo.
DPR-69 is hereby amended to read as follows:
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(E).T,eg,h n,ig,a,1,,Sppy,i,f i _ca t i o n s The Technical Specifications contained in Appendices A and B, as revised through Aoiendment No.137, are hcreby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license aniendment is effective as of the date of its issuance and shall be implenented within 30 days.
FOR THE NUCLEAR RECULATORY COMMISSION dn 4 /. 6.4./L l
Robert A. Capra, Director Project Directorate 1-1 Division of Peactor Projects - 1/11 Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance:
July 30,1991 l
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ATTACHMENT 70 tICENSE AMENDMENTS
, AMENDMENT NO.157 FACILITY _ OPERATING LICENSE NO. 0PR-53 AMENDMENT NO. 137 FACILITY OPERATING LICEhSE NO. DPR-69 DOCKET NOS 50-317 AND 50-318 Revise Appendix A as follows:
Remove Pages Insert Pages 3/4 6-1*
3/4 6-1*
3/4 6-2 3/4 6-2
- Pages that did not change, but are overleaf i.
i i
i.
e 3/4.6 CONTAltiMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT CONTAINMENT INTEGRITY LitiL11tiLCSlfQlT10N FOR OPERATION 3.6.1.1 Pr imary CONTAINMENT INTEGRITY shall be maintained.
APPLICAELLL11: MODES 1, 2, 3 and 4.
ACTION:
Without primary CONTAINMENT INTEGRITY, restore CONTAINNENT INTEGRITY within one hour 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 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 />.
EURE1LLA!iCLREQVlREMENTS 4.6.1.1 Primary CONTAINMENT INTEGRITY shall be demonstrated:
a.
At least once per 31 days by verifying that il penetrations
- not capable of being closed by OPERABLE containment automatic isolation valves and required to be closed during accident conditions are closed by valves, blind flanges, or deactivated automatic valves secured n their positions, except as provided in Table 3.6-1 of Specification 3.6.4.1.
b.
By verifying that each containment air lock is in compliance with the requirements of Specification 3.6.1.3.
c.
By verifying that the equipment hatch is closed and scaled, prior to entering H0DE 4 following a shutdown where the equipment hatch was opened, by conducting a Type B test per Appendix J to 10 CFR Part 50.
Except valves, blind flanges, and deactivated automatic valves which are located inside the containment and are locked, sealed, or otherwise secuted in the closed position. These penetrations shall be verified closed during each COLD SHUTDOWN except that such verification need not be performed more often than once per 92 days, l
CALVERT CLIFFS - UNIT 1 3/4 6-1 Amendment No E M J7,153 1
CONTAINMENT SYSTEMS CONTAINMENT LEAKAGE LlHLTING CONDITION FOR OPERATION 3.6.1.2 Containment leakage rates shall be limited to:
a.
An overall integrated leakage rate of:
1.
5L (346,000 SCCM), 0.20 percent by weight of the conlainment' air per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at P, 50 psig, or 2.
sLt (61,600 SCCM), 0.058 percent by weight of the containment air per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at a reduced pressure of P.
25 psig.
t b.
A combined leakage rate of 5 0.60 L penetrationsandvalvessubjecttotyp(207,600 SCCM), for all e B and C tests when pressurized to P,.
APPLICABILITY: MODES 1, 2, 3 and 4.
ACTION:
With either (a) the measured overall integrated containment leakage rate exceeding 0.75 L (259,500 SCCM) or 0.75 Lt (46,200 SCCM) -as applicable, or (b valves) with the measured combined leakage rate for all penetrations and subject to Types B and C tests exceeding 0.60 L, restore the leakagerate(s)towithinthe-limit (g)priortoincreasingtheReactor Coolant System temperature above 200 F -
SURVEILLANCE RE0VIREMENTS
==
4.6.1.2 The containment leakage rates shall be demonstrated at the following test schedule and shall be determined in conformance with the criteria, methods and provisions specified in Appendix J of 10 CFR Part 50:
Three Type A tests (Overall Integrated Containment Leakage a.
Rate) shall be conducted at approximately equal intervals during shutdown at either P t (25 psig)-
during each 10-year service pe(50 psig) or at P a
riod.
CALVERT CLIFFS - UNIT 1 3/4 6 Amendment No. 75/95/JJ2,157
s 3/4.6 CONTAINMENT SYS7rg O
3f J.1 PRIMARY CONIA:
El CONTAINMENT INTEGRITY LIMITING CONDITION F0fLOPERAT10N 3.6.1.1 Primary CONTAINMENT INTEGRITY shall be maintained.
APPLICABILITY: MODES 1, 2, 3 and 4.
ACTION:
Without primary CONTAINNENT INT [GRITY, restore CONTAINMENT INTEGRITY within one.our 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 in COLD SHU1DOWN within tie following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
MHlLLANCEREQUIREMENTS 4.6.1.1 Primary CONTAINNENT INTEGRITY shall be demonstrated:
a.
At least once per 31 days by verifying that all penetrations
- not capable of being closed by OPERABLE containment automatic isolation >alves and requim d to be closed during accident conditions are closed by v. wes, blind flanges, or deactivated automatic valves secured in their positions, except as provided in Table 3.6-1 of Specificetion 3.6.4.1.
b.
By verifying that each containment air lock is in compliance with the requirements of Specification 3.6.1.3.
c.
By verifying that the equipment hatch is closed and sealed, prior _ to entering _ MODE 4 following a shutdown where the equipment hatch was opened, by conducting a Type B test per Appendix J to 10 CFR Part 50.
Except valves, blind flanges, and dectivated automatic valves which are located inside the containment..; are locked, sealed, or otherwise secured in the closed position.
These penetrations shall be verified closed during each COLD SHUTDOWN except tf
- such verification need not be performed more often than or per 92 days.
CALVERT CLIFFS - UNIT 2 3/4 6 1 Amendment No J/JJ/JJ,136
l e
CONTAINMENT SYSTEMS CONTAINMENT LEAKAGE i
LIMIIM.10@1110N FOR OPERAT10N 3.6.1.2 Containment leakage rates shall be limited to:
a.
An overall integrated leakage rate of:
1.
$L 346.000 SCCM), 0.20 percent by weight of the conta(inmentairper24hoursatP,50psig,or 2.
1 L, (44,600 SCCM), 0.042 percent by weight of the containment air per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at a reduced pressure of P '
25 psig.
t b.
A combined leakage rate of 5 0.60 L penetrationsandvalvessubjecttotyp(207,600SCCM) for all e B and C tests when pressurized to P '
a APPLICABILITY: MODES 1, 2, 3 and 4.
ACTION:
With either (a) the measured overall integrated containment leakage rate exceedin 0.75 L 259.500 SCCM), or 0.75 Lt applicabe,or($)(withthemeasuredcombined(33,400SCCM),as leakage rate for all penetrations and valves subject to Types B and C tests exceeding 0.60 L '
a restore the leakage rate (s) to within the limit (s) srior to increasing the Reactor Coolant System temperature a)ove 200 F.
0 SURVEILLANCE RE0VIREMENTS a
4.6.1.2 The containment leakage rates shall be demonstrated at the -
following test schedule and shall be determined in conformance with the criteria, methods and provisions specified in Appendix J of 10 CFR Part 50:
Three Type A tests (Overall Integrated Containment Leakage a.
Rate) shall be conducted at approximately equal intervals during shutdown at either P during each 10 year service (50 psig) or at Pt (25 psig) period.
CALVERT CLIFFS - UNIT 2 3/4 6 2 Amendment No. JJ###J,137
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