ML20086J879
| ML20086J879 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 01/11/1984 |
| From: | Vassallo D Office of Nuclear Reactor Regulation |
| To: | Carolina Power & Light Co |
| Shared Package | |
| ML20086J885 | List: |
| References | |
| DPR-62-A-091, DPR-71-A-065 NUDOCS 8401250450 | |
| Download: ML20086J879 (14) | |
Text
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.o UNITED STATES
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- c. c ',j NUCLEAR REGULATORY COMMISSION
.. E WASHINGTON, D. C. 20555 g i
Q>a f CAROLINA POWER & LIGHT COMPANY DOCKET NO. 50-325 RRUNSWICK STEAM ELECTRIC PLANT, UNIT 1 Af1ENDMENT TO FACILITY OPERATING LICENSE Amer.dment No. 65 License No. DPR-71 1.
The riuclear Regulatory Comission (the Commission) has found that:
A.
The application for amendment by Carolina Power & Light Company
.(the licensee) dated October 3, 1983' complies with the standards and requirements of the Atomic Energy Act of 1954, as amended j
.(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 rul'es 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. sill 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 recuirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachnent to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-71 is hereby amended to read as follows:
8401250450 840111 PDR ADOCK 05000324 P.
. 2.
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 65, 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 C0tiMISSION Domenic B. Vassallo, Chief Operat'ing' Reactors Branch #2 Division of Licensing
Attachment:
Changes to the Technical Specifications
~
Date of Issuance:
January 11, 1984 i
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ATTACHMENT TO LICENSE AMENDMENT NO. 65 FACILITY OPERATING LICEtiSE NO. OPR-71 DOCKET NO. 50-325 Remove Insert 3/4 6-2 3/4 6-2 3/4 6-3 3/4 6-3 3/4 6-3A 3/4 6-3A B3/4 6-1 B3/4 6-1
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CONTAIM4ENT SYSTEMS-
~ PRIMARY CONTAI! MENT LEAKAGE LIMITING CONDITION FOR OPERATION 3.6.1.2 Primary containment leakage rates shall-be limited to:
a.
An overall integrated leakage rate of:
containmentairper24$o.0.5percentbyweigatofthe 1.
Less than or equal to L urs at P,,
49 psig, or 2.
Less than or equal to L, 0.357 pere,ent by weight of the g
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 '
t 25 psig.
b.
A combined leakage rate of less than or equal to 0.60 L, f or all
~
penetrations and all valves listed in Table 3.6.3-1, except for main steam line isolation valves *, subject to Type B and C tests when pressurized to P,,
25 psig.
c.
- Less than or equal to 11.5 scf per hour for any one main steam line -
isolation valve when tested at 25 psig.
APPLICABILITY:
When PRIMARY CONTAINMENT INTEGRITY is required per Specification.3.6.1.1.
. ACTION:
With:
a.
The measured overall integrated primary containment leakage rate exceeding 0.75 L, or 0.75 L, as. applicable or g
b.
The measured combined leakage rate f or all penetrations and all valves listed in Table 3.6.3-1, except for main steam line isolation valves *, subject to Type B and C tests exceeding.0.60 L,,
or i-c.
The measured leakage rate exceeding 11.5 scf per hour for any one main steam line isolation valve, l
restore:
a.
The overall integrated leakage rate (s) to less than or equal to 0.75 L, or 0.75,L, as applicable, and t
b.
The combined leakage rate f or all penetrations and all valves listed in Table 3.6.3-1, except for main steam line isolation valves *,
subject'to Type B and C tests to less than or equal to 0.60 L,, and
- Exemption to Appendix "J" of 10 CFR 50.
t BRUNSWICK - UNIT 1 3/4 6-2 Amendment No. 65
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CONTAI! MENT SYSTEMS LIMITING CONDITION FOR OPERATION (Continued)
. ACTION (Continued) c.
The leakage rate to less than or equal to 11.5 sef per hour for any one main steam line isolation valve, prior to increasing reactor coolant system temperature above 212*F.
i SURVEILLANCE REQUIREMENTS
'4.6.1.2 The primary containment leakage rates shall be demonstrated at the 4
following test schedule and shall be determined in conformance with the criterla specified in Appendix J of 10 CFR 50 using the methods and provisions of' ANSI.N45.4 - 1972:
Three Type A Overall Integrated Containment Leakage Rate tests sh'all a.
be conducted at 40 i 10 month intervals during shutdown at P,,
49 psig, or P, 25 psig, during each 10-year service period.
The t
third test of each' set shall be conducted during the shutdown for the 10-year plant inservice inspection.
b.
'If any periodic Type' A test fails to meet either. 0.75 L or 0.75 L,-
a e
the test schedule for subsequent Type A tests shall be reviewed and 4
approved by the Commission.
If two consecutive Type A tests fail to meet 0.75 L, or 0.75 L, a Type A test shall be performed _at each t
plant shutdown for refueling or every 18 months, whichever occurs first, _ until two consecutive Type A tests meet 0.75 L, or 0.75 L ' at t.
which time the above test schedule may be resumed.
c.
The accuracy of each Type A test shall be verified by a supplemental test which:
1.
Confirms the accuracy of the test by verifying that the difference between the supplemental data and the Type A test data is within 0.25 L, or 0.25 L
- t 2.
Has duration sufficient to establish accurately the change in leakage rate between the Type A test and the supplemental test.
3.
Requires the quantity of gas-injected into the containment or bled f rom the containment during the supplemental test to be equivalent to at least 25 percent of the total me.asured leakage at P,,
49 psig or P, 25 psig.
t I
i BRUNSWICK - UNIT 1-3/46-3 Amendment No. 65 t
- _.. - -. _.. - _ _. - -, _.,, _ - ~ -
9 CONTAINMENT SYSTEMS SURVEILLANCE REOUIREMENTS (Continued) d.
Type B and C tests shall be conducted with gas at P,,
49 psig, at intervals no greater than 24 months except for tests in rolving:
1.
Air locks, 2.
Main steam line isolation valves, Air locks shall be tested and demonstrated CPERABLE per Surveillance e.
Requirement 4.6.1.3.
f.
Main steam line isolation valves shall be leak tested at least once per 18 months.
g.
All test leakage rates shall be calculated using observed data converted to absolute values.
Error analyses shall be performed to select a balanced integrated leakage measurement system.
h.
The provisions of Specification 4.0.2 are not applicable to 24 month -
and 40 i 10 month surveillance intervals.
t BRUNSWICK - UNIT 'l 3/4 6-3A Amendment No.
65
3/4.6 CONTAINMENT SYSTEMS BASES 3/4.6.1 PRIMARY CONTAINMENT 3/4.6.1.1 PRIMARY CONTAINMENT INTEGRITY Primary CONTAINMENT INTEGRITY ensures that the release of radioactive materials from the containment atmosphere will be restricted to those leakage
.p'aths and associated leak rates assumed in the accident analyses. This restriction, in conjunction with the leakage rate limitation, will limit the site boundary radiation doses to within the limits of 10 CFR Part 100 during accident conditions.
3/4.6.1.2 PRDfARY CONTAINMENT LEAKAGE
. The limitations on primary containment leakage rates ensure that the total l
containment leakage volume will not exceed the value assumed in the accident
. analyses at the peak accident pressure of 49 psigi P. As an added
'a conservatism, the measured overall integrated leakage rate is further limited to less than or equal to 0.75 L, or 0.75 L, as applicable, during performance -
t of the periodic tests to account for possible degradation of the containment
. leakage barriers between leakage ~ tests.
Operating experience with the main steam line isolation valves has
- indicated that degradation has occasionally occurred in the leak tightness of the valves; therefore, the special requirement for testing these valves.
'The surveillance testing for neasuring leakage rates is consistent with the requirements of Appendix "J" of 10 CFR Part 50 with the exception of exenptions granted for main steam isolation valve leak testing and testing the airlocks after each opening.
3/4.6.1.'3 PRIMARY CONTAINMENT AIR LOCKS The limitations on closure and leak rate for the containment air locks are required to meet the restrictions on PRIMARY CONTAINMENT INTEGRITY and leak rate given in Specifications 3.6.1.1 and 3.6.1.2.
The specification makes allowances for the fact that there may be long periods of time when the air locks will be in a. closed and secured position during reactor operation.
f BRUNSWICK - UNIT 1 B 3/4 6-1 Amendment No. 65
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UNITED STATES j! y
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NUCLEAR REGULATORY COMMISSION
'3 WASHINGTON, D. C. 20555
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CAROLINA POWER.& LIGHT COMPANY DOCKET NO. 50-324
- BRUNSWICK STEAM ELECTRIC PLANT, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 91 License No. DPR-62 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Carolina Power & Light Company (the licensee) dated October 3,1983 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 apolication, the pro *iisions 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 reauirenents I
have been satisfied.
l 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, l
and paragraph 2.C.(2) of Facility Operating License No. DPR-62 is l
hereby amended to read as follows:
f i
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. 2.
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 91, are hereby incorpnrated 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 COMfilSSION I
i
,/
Domenic B. Vassallo, Chief Operating Reactors Branch #2 Division of Licensing
Attachment:
Changes to the.
Technical Specifications Date of Issuance:
January ll, -1984 N
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ATTACHMENT TO LICENSE AMENDMENT N0. 91 FACILITY OPERATING LICENSE NO. 0>R-62 DOCKET N0. 50-324
. Remove Insert 3/4 6-2 3/4 6-2 3/4 6-3 3/4 6 3/4 6-3A
- 3/4 6-3A B3/4 6-1 B3/4 6-1 i
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CONTAI!@ LENT SYSTEMS PRIMARY CONTAINMENT LEAKAGE LIMITING CONDITION FOR OPERATION
- 3. 6.1. 2 Primary containment leakage rates _ shall be limited to:
a.
An overall integrated leakage rate of:
1.
Less than or equal to L 0
containment air per 24 $o,urs.5 percent by weight of the at P, 49 psig, or a
2.
Less than or equal to L, 0.357 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 '
t 25 psig.
b.-
A combined leakage rate of less than or equal to 0.60 L, for all penetrations -and all valves listed in Table 3.6.3-1, except for main steam line isolation valves *, subject to Type B and C tests when pressurized to P,,
25 psig.
- Less than or equal to 11.5 scf per hour f or any one main steam line c.
isolation valve whe'n tested at 25 psig.
APPLICABILITY: When PRIMARY CONTAINMENT INTEGRITY is required per Specification 3.6.1.1.
ACTION:
'With:
The measured overall integrated primary containment leakage rate a.
exceeding 0.75 L, or 0.75 L, as applicable, or "
e b.
The measured combined leakage rate for all penetratio's and all n
valves listed in Table 3.6.3-1, cxcept for main steam line isolation valves *, subject to Type B and C tests exceeding 0.60 L,, or c.
The measured leakage rate exceeding 11.5 scf per hour for any one main steam line isolation valve, restore:
a.
T1.e overall integrated leakage rate (s) to less than or equal to 0.75 L, or 0.75 L, as applicable, and t
b.
The combined leakage rate f or all penetrations and all valves listed in Table 3.6.3-1, except for main steam line isolation valves *,
subject to Type B and C tests to less tF in or equal to 0.60 L,, and
- Exemption to Appendix "J" of 10 CF7 50.
1 I
BRUNSWICK - UNIT 2 3/4 6-2 Amendment No. 91
~
CONTAIM4ENT SYSTEMS LIMITING CONDITION FOR OPERATION (Continued)
ACTION (Continued) c.
The leakage rate to less than or equal to 11.5 scf per hour for any one main steam line isolation valve, prior to increasing reactor coolant system temperature above 212*F.
SURVEILLANCE REQUIREMENTS 4.6.1.2 The primary containment leakage rates shall be demonstrated at the following 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 ANSI N45.4 - 1972:
Three Type A Overall Integrated Containment Leakage Rate. tests shall
-a.
be conducted at 40 i 10 month intervals during shutdown at P,,
49 psig, or P, 25 psig, during each 10 year service period.
The t
third test of each set shall be conducted during the shutdown for the 10-year plant inservice inspection.
If any periodic Type A se't fails to meet either 0.75 L,or 0.75 L b.
s the test schedule for subsequent Type A tests shall be reviewed anb, approved by the Commission.
If two consecutive Type A tests f ail to meet 0.75 L or 0.75 L, a Type A test shall be performed at each a
plant shutdown for refueling or every 18 months, whichever occurs first, until two consecutive Type A tests meet 0.75 L or 0.75 L, at a
t which time the above test schedule may be resumed.
The accuracy of each Type A test shall be verified by a supplemental
- c. -
test which:
1.
Confirms the accuracy of the test by verifying that the difference between the supplemental data and the Type A test data is within 0.25 L r 0.25 L.
a t
2.
Has duration sufficient to establish accurately the change in leakage rate between the Type A test and the supplemental test.
3.
Requires the quantity of gas injected into the containment or l
bled f rom the containment during the supplemental test to be equivalent to at least 25 percent of the total measured leakage I
at P, 49 psig or P, 25 psig.
3 t
BRUNSWICK - UNIT 2 3/46-3 Amendment No. 91
CONTAINMENT SYSTEMS SURVEILLANCE REOUIREMENTS (Continued) d.
Type B and C tests shall be conducted with gas at P, 49 psig, at intervals no greater than 24 months except for tests involving:
1.
Air locks, a
2.
Main steam line isolation valves, Air locks shall be tested and demonstrated OPERABLE per Surveillance e.
Requirement 4.6.1.3.
f.
Main steam line isolation valves shall be leak tested at least once per 18 months.
g.
All test leakage rates shall be calculated using observed data converted to absolute values. E,rror analyses'shall be performed to select a balanced integrated leakage measurement system.
h.
The provisions of Specification 4.0.2 are not applicable to 24 month and 40 t 10 month surveillance intervals.
BRUNSWICK - UNIT 2 3/4 6-3A Amendment No. 91
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3/4.6 CONTAINMENT SYSTEMS BASES-
'3/4.6.1-PRIMARY CONTAINMENT 3/4.6.1.1 -PRIMARY CONTAINMENT INTEGRITY Primary CONTAINMENT INTEGRITY ensures that the release.of radioactive materials from the containment atmosphere will be restricted to those leakage paths and associated leak rates assumed in the accident analyses. This restriction, in conjunction with.the leakage rate limitation, will limit'the site boundary radiation doses to within the limits of 10 CFR Part 100 during accident conditions.
3/4.6.1.2 LPRIMARY CONTAINMENT LEAKAGE The limitations on primary containment leakage rates ensure that the total l
containment' leakage volume will not exceed the value assumed in the accident analyses at the peak accident pressure of 49 psig, P. As an added a
conservatism, the measured overall integrated leakage rate is further limited -
to less than or equal to 0.75 L, or 0.75 L, as applicable, during performance t
of the periodic tests to account-for possible ' degradation of the containment leakage barriers between leakage tests.
' Operating: experience with -the main steam line isolation valves has.
indicated that degradation has occasionally occurred in the leak tightness of the valves;. therefore, the special requirement for testing these valves.
The surveillance testing for measuring leakage rates is consistent with the requirements. of Appendix "J" of 10 CFR Part 50 with-the exception of exemptions granted for main-steam isolation valve leak testing and testing the airlocks af ter each opening.
3/4.6.1.3 PRIMARY CONTAINMENT AIR LOCKS The limitations on closure and leak rate for the containment air locks are required to meet the restrictions on PRIMARY CONTAINMENT INTEGRITY and leak rate given in Specifications 3.6.1.1 and 3.6.1.2.
The specification makes allowances for the fact that there may be long periods of time when the air locks will be'in a closed and secured position during reactor operation.
BRUNSWICK - UNIT 2 B 3/4 6-1 Amendment No. 91
_ _ _ _ _ _ _ _ _ _ _ _ _ -