ML20141K090
| ML20141K090 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 01/08/1986 |
| From: | Thadani A Office of Nuclear Reactor Regulation |
| To: | Baltimore Gas & Electric Co (BGE) |
| Shared Package | |
| ML20141K093 | List: |
| References | |
| DPR-53-A-112, DPR-69-A-095 NUDOCS 8601220205 | |
| Download: ML20141K090 (10) | |
Text
.# "%,)g UNITED STATES 8
NUCLEAR REGULATORY COMMISSION o
E WASHINGTON, D. C. 20555 l
g,*****/
BALTIMORE GAS AND ELECTRIC COMPANY DOCKET NO. 50-317 CALVERT CLIFFS NUCLEAR POWER PLANT UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.112 License No. DPR-53 1.
The Nuclear Regulatory Comission 'the Comission) has found that:
s A.
The application for amendment by Baltimore Gas & Electric Company (the licensee) dated April 26, 1985, complies with the standards 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 I; B.
The facility will operate in conformity'with the application, the provisions of the Act, and the rules and regulations of the Comission; 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 with the Comission's regulations; D.
The issuance of this amendment will not be inimical to the comon 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 Comission's regulations and all applicable requirements have been satisfied.
I i
8601220205 B60100 DR ADOCK O 37 1
. 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.(?) of Facility Operating License No. DPR-53 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.112, 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 rf.h Asho C. Thadani, Of rector PWR roject Directorate #8 Division of PWR !.icensing-B
Attachment:
Changes to the Technical Specifications Date of Issuance: January 8,1986 t
f w
I t
l
4 ATTACHMENT TO LICENSE AMENDMENT NO.112 t
FACILTIY OPERATING LICENSE NO. DPR-53 DOCKET NO. 50-317 Replace the following page of the Appendix "A" Technical Specifications with the enclosed page. The revised page is identified by amendment number and contains vertical lines indicating the areas of change. The corresponding overleaf page is provided to maintain document completeness.
Remove Page Insert Page 3/4 6-2 3/4 6-2 l
l
\\
3/4.6 CONTAINMENT SYSTEMS 3/4. 6.1 PRIMARY CONTAINMENT CONTAINMENT INTEGRITY LIMITING CONDITION FOR OEPRATION 3.6.1.1 Primary CONTAINMENT INTEGRITY shall be maintained.
APPLICABILITY: MODES 1, 2, 3 and 4.
ACTION:
Without primary CONTAINMENT INTEGRITY, restore CONTAINMENT 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 />.
SURVEILLANCE REQUIREMENTS 4.6.1.1 Primary CONTAINMENT 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 valves and required to be closed during accident conditions are closed by valves, blind flanges, or deactivated automatic valves secured in their positions, except as provided in Table 3.6-1 of Specification 3.6.4.1.
I b.
Bv.erifying that each containment air lock is OPERABLE per 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 deactivated automatic valves which are located inside the containment and are locked, sealed, or otherwise secured 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. 8 3 i
i CONTAINMENT SYSTEMS CONTAINMENT LEAKAGE LIMITING CONDITION FOR OPERATION 3.6.1.2 Containment leakage rates shall be limited to:
a.
An overall integrated leakage rate of:
1 L,pe(r 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at P, 50 psig, or346,000 SCCM), 0.20 percent by 1.
air a
2.
1Lt (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 10.60 L (207,600 SCCM), for all penetra-tions and valves subject to Type B $nd C tests when pressurized to P.
3 APPLICABILITY: MODES 1, 2, 3 and 4.
ACTION:
With either (a) the measured overall integrated containment leakage rate or (b) with the $ea(259.500sured combined leakage fate for all penetrations exceeding 0.75 L SCCM) or 0.75 L (46,200 SCCM), as applicable, subject to Types B and C tests exceeding 0.60 L, restore the leakage rate (s) to within the limit (s) prior to increasing the Reactor Coolant System temperature above 200*F.
SURVEILLANCE REQUIREMENTS 4.6.1.2 The containment leakage rates shall be demonstrated at the follow-ing test schedule and shall be determined in conformance with the criteria
~
specified in Appendix J of 10 CFR Part 50 using the methods and provisions
[
of ANSI N45.4 - 1972:
Three Type A tests (overall Integrated Containment Leakage Rate) a.
shall be conducted at 40 + 10 month intervals during shutdown at either Pa (50 psig) or at Pt (25 psig) during each 10-year service period.
1
'1 CALVERT CLIFFS - UNIT 1 3/4 6-?
AmendmentNo.75,fd[,112
%^
UNITED STATES
~!"
NUCLEAR REGULATORY COMMISSION l
n
.R WASHINGTON, D. C. 20555
%,**.../
BALTIMORE GAS AND ELECTRIC COMPANY DOCKET NO. 50-318 CALVERT CLIFFS NUCLEAR POWER PLANT UNIT N0. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 95 License No. DPR-69 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Baltimore Gas & Electric Company (the licensee) dated April 26, 1985, complies with the standards 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 I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; j
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 with the Comission'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 Comission's regulations and all applicable requirements have been satisfied.
1 f
. 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 Appendix A, as revised through Amendment No. 95, 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 CLEAR REGULATORY COMMISSION LM^'"~
Ashok C. Thadani, Director PWR roject Directorate #8 Division of PWR Licensing-B
Attachment:
Changes to the Technical Specifications Date of Issuance: January 8, 1986
ATTACHMENT TO LICENSE AMENDMENT NO. 95 FACILTIY OPERATING LICENSE NO. DPR-69 DOCKET NO. 50-318 Replace the following page of the Appendix "A" Technical Specifications with the enclosed page. The revised page is identified by amendment rumber and contains vertical lines indicating the areas of change. The corresponding overleaf page is provided to maintain document completeness.
Remove Page Insert Page 3/4 6-2 3/4 6-2 l
\\
1 1
4 A,?
l
-=
^
l i
3/4.6 CONTAINMENT SYSTEMS 3/4. 6.1 PRIMARY CONTAINMENT CONTAINMENT INTEGRITY c
LIMITING CONDITION FOR OEPRATION 1
- 3. 6.1.1 Primary CONTAINMENT INTEGRITY shall be maintained.
APPLICABILITY: MCDES 1, 2, 3 and 4.
ACTION:
l Without primary CONTAINMENT INTEGRITY, restore CONTAINMENT 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 i
SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
j SURVEILLANCE REQUIREMENTS i
4.6.1.1 Primary CONTAINMENT INTEGRITY shall be demonstrated:
i a.
At least once per 31 days by verifying that all 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 in their positions, except as provided I
in Table 3.6-1 of Specification 3.6.4.1.
l b.
By verifying that each contaimnent air lock is OPERABLE per Specification 3.6.1.3.
c.
By verifying that the equipment hatch is closed and sealed, prior to entering fiode 4 following a shutdown where the equipnent hatch was opened, by conducting a Type B test per Appendix J to 10 CFR Part 50.
4
- Except valves, blind flanges, and deactivated automatic valves which are located inside the containment and are locked, sealed, or otherwise secured in the closed position.
These penetrations shall be verified closed during each COLD SHUTDOWN except that such verification need not be performed more 4
often than once per 92 days.
CALVERT CLIFFS - UNIT 2 3/4 6-1 Amendment No. 4, 6 C l
=
L CONTAINMENT SYSTEMS CONTAINMENT LEAKAGE i
LIMITING CONDITION FOR OPERATION 3.6.1.2 Containment leakage rates shall be limited to:
a.
An overall integrated leakage rate of:
l 1.
<La (346,000 SCCM), 0.20 percent by weight of the containment l
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 I
2.
<Lt (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 < 0.60 L (207,600 SCCM) for all penetra-tionsandvalvessubjecttoTypeB$ndCtestswhenpressurizedtoP,.
APPLICABILITY: MODES 1, 2, 3 and 4.
ACTION:
With either (a) the measured overall integrated containment leakage rate or (b) with the 8ea(259.500sured combined leakage rite for all penetrations and exceeding 0.75 L SCCM), or 0.75 L (33,400 SCCM), as applicable, valves subject to Types B and C tests exceeding 0.60 L, Reactor Coolant Syst
, restore the leakage rate (s) to within the limit (s) prior to increasing the temperature above 200"F.
i SURVEILLANCE REQUIREMENTS l
4.6.1.2 The containment leakage rates shall be demonstrated at the follow-ing test schedule and shall be determined in conformance with the criteria specified in Appendix J of 10 CFR 50 using.the methods and provisions of l
ANSI N45.4 - 1972:
I Three Type A tests (Overall Integrated Containment Leakage Rate) a.
shall be conducted at 40 + 10 month intervals during shutdown at i
either Pa (50 psig) or at'~Pt (25 psig) during each 10-year service period.
1 l
i CALVERT CLIFFS - UNIT 2 3/4 6-2 Amendment No. 56, /.0,95
.