ML20066B366
| ML20066B366 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 10/13/1982 |
| From: | Clark R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20066B368 | List: |
| References | |
| NUDOCS 8211060582 | |
| Download: ML20066B366 (10) | |
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION 3
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BALTIMORE GAS AND ELECTRIC COMPANY
-- DOCKET-NO. 50-317 CALVERT CLIFFS NUCLEAR POWER PLANT UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 79 License No. DPR-53 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by btitimore Gas & Electric Company (the licensee) dated September 22, 1982, 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.
8211060582 821013 PDR ADOCK 05000317 P
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2-2.
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-53 is hereby amended te. read as follows:,
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 79, 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 the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION dd Ro ert A. Clark, Chief Operating Reactors Branch #3 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: October 13, 1982 4
ATTACHMENT TO LICENSE AMENDMENT NO. 79 FACILITY OPERATING LICENSE NO. DPR-53 DOCKET NO. 50-317 Replace the following page of the Appendix A Technical Specifications with the enclosed page as indicated. The revised page is identified by Amendment-number and contains vertical lines indicating the area of change. The corresponding overleaf page is also provided to maintain document completeness.
Page 3/4 6-18 e
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CONTAINMENT SYSTEMS 3/4.6.4 CONTAINMENT ISOLATION VALVES LIMITING CONDITION FOR OPERATION 3.6.4.1 The containment isolation valves specified in Table 3.6-1 shall be OPERABLE with isolation times as shown in Table 3.6-1.
APPLICABILITY: MODES 1, 2, 3 and 4.
ACTION:
With one or more of the isolation valve (s) specified in Table 3.6-1 inoperable, either:
a.
Restore the inoperable valve (s) to OPERABLE status within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, or b.
. Isolate each affected penetration 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 one deactivated automatic valve secured in the isolation position, or c.
Isolate the affected penetration 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 one closed manual valve or blind flange; or d.
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 />.
SURVEILLANCE REQUIREMENTS i
4.6.4.1.1 The isolation valves specified in Table 3.6-1 shall be demon-strated OPERABLE prior to returning the valve to service after maintenance, repair or replacement work is performed on the valve or its associated actuator, control or power circuit by performance of a cycling test and verification of isolation time.
CALVERT CLIFFS - UNIT 1 3/4 6-17
CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) 4. 6. 4.1. 2 Each isolation valve specified in Table 3.6-1 shall be demonstrated OPERABLE during the COLD SHUTDOWN or REFUELING MODE at least once per 18 months by:
a.
Verifying that on each containment isolation Channel A or Channel B test signal, each required isolation valve actuates to its. isolation position.
b.
Verifying that on each Containment Radiation-High Test Channel A or Channel B test signal, both required containment purge valves actuate to their isolation position.
c.
Verifying that on each Safety Injection Actuation Channel A or Channel B test signal, each required isolation valve actuates to its isolation position.
- 4. 6. 4.1. 3 The isolation time of each power operated or automatic valve of Table 3.6-1 shall be determined to be within its limit when tested pursuant to Technical Specification 4.0.5.
4.6.4.1.4 Containment purge isolation valves shall be demonstrated OPERABLE any time upon entering MODE 5 from power operation modes, unless the last surveillance test has been performed within the past 6 months or any time after being opened and prior to entering MODE 4 from shutdown modes by verifying that when the measured leakage rate is added to the leakage rates determined pursuant to Technical Specification 4.6.1.2.d for all other Type B or C penetrations, the combined leakage rate is less than or equal to 0.60 La (207,600 SCCM). The leakage rate for the centainment purge isolation valves shall also be compared-to the previously measured leakage rate.to detect excessive valve degradation.
- 4. 6. 4.1. 5 The containment purge isolation valve seals shall be replaced with new seals at a frequency to ensure no individual seal remains in service greater than 2 consecutive fuel reload cycles.
CALVER1 CLIFFS - UNIT 1 3/4 6-18 Amendment No. pg, BA/, 79
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UNITED STATES hr NUCLEAR REGULATORY COMMISSION j
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BALTIM0RE GAS AND ELECTRIC COMPANY
. DOCKET JUD. 50-318 CALVERT CLIFFS NUCLEAR POWER PLANT UNIT N0. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 59 License No. OPR-69 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Baltimore Gas & Electric
- Company (the licensee) dated September 22, 1982, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (tha Act) and tha Commissibn'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 (1) 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 a
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 l
E.
The issuance of this amendme.it is in accordance with 10 CFR l
Part 51 of the Commission's regulations and all applicable l
requirements have been satisfied.
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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-69 is hereby. amended to. read as follows:
2.
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 59, 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 the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
[
]
U Robert A. Clark, Chief Operating Reactors Branch #3 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: October 13, 1982 l
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ATTACHMEhT TO LICENSE AMENDMENT N0. 59 '
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FACILITY OPERATING LICEN$C NO. DPk-69 DOCKET N0. 50-318 Replace the following page of the Appendix A Technical Specifications with the enclosed page as indicated.
The revised page is identified by Amendment number and contains vertical lines indicating the area of change. The corresponding overleaf page is also provided to maintain document completeness.
Page 3/4 6-18 O
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CONTAINMENT SYSTEMS 3/4.6.4 CONTAINMENT ISDLATION VALVES LIMITING CONDITION FOR OPERATION - -
3.6.4.1 The containment isolation valves specified in Table 3.6-1 shall be OPERABLE with isolation times as shown in Table 3.6-1.
APPLICABILITY: MODES 1, 2, 3 and 4.
ACTION:
With one or more of the isolation valve (s) specified in Table 3.6-1 inoperable, either:
a.
Restore the inoperable valve (s) to OPERABLE status within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, or b.
Isolate each affected penetration 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 one deactivated automatic valve secured in the isolation position, or c.
Isolate the affected penetration 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 one closed manual valve or blind flange; or d.
Be in at least HOT STANDBY within.he next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD t
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 4.6.4.1.1 The isolation valves specified in Table 3.6-1 shall be demon-strated OPERABLE prior to returning the valve to service after maintenance, repair or replacement work is performed on the valve or its associate'd actuator, control or power circuit by performance of a cycling test and verification of isolation time.
CALVERT CLIFFS - UNIT 2 3/4 6-17
~
CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)
- 4. 6. 4.1. 2 Each isolation valve specified in Table 3.6-1 shall be demonstrated OPERABLE during the COLD SHUTDOWN or REFUELING MODE at least once per 18 months by:
a.
Verifying that on each containment isolation Channel A or Channel B test signal, each required isolation valve actuates to its isolation position.
b.
Verifying that on each Containment Radiation-High Test Channel A or Channel B test signal, both required containment purge valves actuate to their isolation position.
c.
Verifying that on each Safety Injection Actuation Channel A or Channel B test signal, each required isolation valve actuates to its isolation position.
- 4. 6. 4.1. 3 The isolation time of each power operated or automatic valve of Table 3.6-1 shall be determined to be within its limit when tested pursuant to Technical Specification 4.0.5.
4.6.4.1.4 Containment purge isolation valves shall be demonstrated OPERABLE any time upon entering MODE 5 from power operation modes, unless the last surveillance test has been performed within the past 6 months or any time
~s after being opened and prior to entering MODE 4 from shutdown modes by verifying that when the measured leakage rate is added to the leakage rates determined pursuant to Technical Specification 4.6.1.2.d for all other Type B or C penetrations, the combined leakage rate is less than or equal to 0.60 La (207,600 SCCM).
The leakage rate for the containment purge isolation valves shall also be compared to the previously measured leakage rate to detect excessive valve ocgradation.
4.6.4.1.5 The containment purge isolation valve seals shall be replaced with new seals at a frequency to ensure no individual seal remains in service greater than 2 consecutive fuel reload cycles.
CALVERT CL:FFS - UNIT 2 3/4 6-18 Amendment No. //7, is,59
.