ML20062E937
| ML20062E937 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 07/30/1982 |
| From: | Clark R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20062E940 | List: |
| References | |
| NUDOCS 8208110002 | |
| Download: ML20062E937 (10) | |
Text
pe" UNITED STATES c
'n NUCLEAR REGULATORY COMMISSION j
'j WASHINGTON, D. C. 20555 o
~
BALTIM0RE GAS AND ELECTRIC COMPANY DOCKET NO. 50-317 CALVERT CLIFFS NUCLEAR POWER PLANT UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 74 License No. DPR-53 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Baltimore Gas & Electric Company (the licensee) dated July 20, 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 th'e 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.
DECIC';ATED ORIGIUAL Cortified By 8208110002 G20730 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 to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through, Amendment No. 74, 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
- f
- c. -
Robert A. Clark, Chief Operating Reactors Branch #3 Division of Licensing
Attachment:
. Changes to the Technical Specifications Date of Issuance: July 30, 1982 1
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ATTACHMENT TO LICENSE AMENDMENT NO. 74 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 6-26
TABLE 3.6-1 (Continued)
CONTAINf1ENT ISOLATI0tl VALVES M
A PENETRATI0tl ISOLATION ISOLATI0ft VALVE ISOLATION n
NO.
CHAfillEL IDENTIFICATION NO.
FUNCTION TIME (SECONDS)
C
?
61 NA 76Y-1 Refueling Pool Outlet NA NA 293M-1 NA
!!A 293M-1 NA E
NA 293f t-1 NA a
.a 62 SIAS A MOV-6579 Containment Heating Outlet
<13 64 NA 238-1 Containment Heating Inlet NA (1). Manual or remote manual valve which is closed during plant operation.
w 2
(2) May be opened below 300 F to establish shutdown cooling flow.
cnL (3)
Containment purge isolation valves will be shut in MODES 1, 2, 3 and 4 per TS 3/4 6.1.7.
l 1
May be open on an intermittent basis under administrative control.
- Containment purge isolation valves isolation times will only apply for MODES 5 and 6 during which time these valves may be opened.
Isolation time.is NA for MODES 1, 2, 3 and 4 per TS 3/4 6.1.7 during which L'
time these valves must remain closed.
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CONTAINMENT SYSTEMS 3/4.6.5 COMBUSTIBLE GAS CONTROL HYDROGEN ANALYZERS LIMITING CONDITION FOR OPERATION 3. 6. 5.1 Two independent containment hydrogen analyzers shall be OPERABLE *.
l APPLICABILITY: MODES 1 and 2.
ACTION:
With one hydrogen analyzer inoperable, restore the inoperable analyzer to OPERABLE status within 30 days 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 />.
SURVEILLANCE REQUIREMENTS
- 4. 6. 5.1 Each hydrogen analyzer shall be demonstrated OPERABLE at least once per 92 days on a STAGGERED TEST BASIS by performing a CHANNEL CALIBRATION using sample gases containing:
a.
Zero volume percent hydrogen, balance nitrogen, and b.
Three volume percent hydrogen, balance nitrogen.
- Until September 30, 1982, one hydrogen analyzer may be made inoperable, at l
any given time, for the purpose of performing modifications relating to TMI Action Plan Item II.F.1.6.
During this time, Specification 3.0.4 is not applicable to this requirement.
CALVERT CLIFFS - UNIT 1 3/4 6-26 Amendment No.'60, 74
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UNITED STATES
[
g NUCLEAR REGULATORY COMMISSION j
WASHINGTON, D. C. 20555 g
r.,
~%.....l BALTIM0RE GAS AND ELECTRIC COMPANY DOCKET N0. 50-318 CALVERT CLIFFS NUCLEAR POWER PLANT UNIT NO. 2 AMEh ?...T TO FACILITY OPERATING LICENSE
~
Amendment No. 55 License No. DPR-69 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Baltimore Gas & Electric Company (the licensee) dated July 20, 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; j
C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without l
(
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 l
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 l
Part 51 of the-Commission's regulations and all applicable l
requirements have been satisfied.
DEGIC:!LTED CRIGIl:AI, Cortifici Dy l
l
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-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. 55, are hereby incorporated in the license. The licensee shall operate the facility in accordance kith the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
'~)
r_ _ -
n._
Robert A. Clark, Chief Operating Reactors Branch #3 Division of Licensing
Attachment:
Changes to the
, Technical Specifications Date of Issuance: July 30, 1982 1
e
ATTACHMENT TO LICENSE AMENDMENT NO. 55 FACILITY OPERATING LICENSE NO. DPR-69 DOCKET NO. 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 6-26 e
e O
I i
TABLE 3.6-1 (Continued) h' CONTAINf1ENT ISOLATION VALVES 9
PENETRATION ISOLATION ISOLATION VALVE ISOLATION' NO.
CilANNEL IDENTIFICATION NO.
FUNCTION TIME (SECONDS)
P M
61 NA 76Y-1 Refueling Pool Outlet NA 3
NA 293M-1 NA i
NA 293M-1 NA c-NA 293fi-1 NA i5
--i 62 SIAS A MOV-6579 Containment lleating Outlet
<13 64 NA 238-1 Containment Heating Inlet NA (1) Manual or remote manual valve which is closed during plant operation.
w (2) May be opened below 300 F to establish shutdown cooling flow.
(3)
Containment purge isolation valv,es will be shut in MODES 1, 2, 3 and 4 per TS 3/4 6.1.7.
l May be open on an intermittent basis under administrative control.
- Containment purge isolation valves isolation times will only apply for MODES 5 and 6 during which time these valves may be opened.
Isolation time is NA for MODES 1, 2, 3 and 4 per TS 3/4 6.1.7 during which time these valves must remain closed.
E g.
-Q
CONTAINMENT SYSTEMS 3/4.6.5 COMBUSTIBLE GAS CONTROL HYDROGEN ANALYZERS LIMITING CONDITION FOR OPERATION
l APPLICABILITY: MODES 1 and 2.
ACTION:
With one hydrogen analyzer inoperable, restore the inoperable analyzer to OPERABLE status within 30 days 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 />.
SURVEILLANCE REQUIREMENTS 4.6.5.1 Each hydrogen analyzer shall be demons'trated OPERABLE at least once per 92 days on a STAGGERED TEST BASIS by performing a CHANNEL CALIBRATION using sample gases containing:
a.
Zero volume percent hydrogen, balance nitrogen, and b.
Three volume percent hydrogen, balance nitrogen.
- Until September 30, 1982, one hydr' ogen analyzer may be made inoperable, at
^ l any given time, for the purpose of performing modifications relating to TMI Action Plan Item II.F.1.6.
During this time, Specification 3.0.4 is
' not applicable to this requirement.
CALVERT CLIFFS - UNIT 2 3/4 6-26 Amendment No.,42, 55 w-.
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