ML20054K653
| ML20054K653 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 06/25/1982 |
| From: | Clark R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20054K654 | List: |
| References | |
| TAC-07711, TAC-08404, TAC-7711, TAC-8404, NUDOCS 8207060024 | |
| Download: ML20054K653 (13) | |
Text
.
O Ma u9'o, UNITED STATES
!i NUCLEAR REGULATORY COMMISSION
{, b> '.-q)/ %
"/
E 9.h'..,[J WASHINGTC N, D. C. 20555 gs.....f WISCONSIN ELECTRIC POWER COMPANY DOCKET N0. 50-266 POINT BEACH NUCLEAR PLANT, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 61 License No. DPR-24 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Wisconsin Electric Power Company (the licensee) dated December 12, 1975 as modified by letters dated July 18, 1977, February 6,1978 and February 25, 1981, 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 confonnity 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 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 amendment is in accordance with 10 CFR Part i
51 of the Commission's regulations and all applicable requirements l
have been satisfied.
DESIGjiATED ORIGINAI, CortifiedEd-- 6 AMid
^NC cy 8207060024 820625 DRADOCKOS000g
. 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.B of Facility Operating License No. OPR-24 is hereby amended to read as follows:
B.
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 61, 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 (t
o obert A. Clark, Chief Operating Reactors Branch #3 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: June 25, 1982 i
k p asouq
! j >., j'\\
UNITED STATES
+
i NUCLEAR REGULATORY COMMISSION
- / \\ * *'.'
E WASHINGTON, D. C. 20555 r
- W ' /pl s\\..w...
WISCONSIN ELECTRIC POWER COMPANY DOCKET NO. 50-301 POINT BEACH NUCLEAR PLANT, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 66 License No. DPR-27 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Wisconsin Electric Power Company (the licensee) dated December 12, 1975 as modified by letters dated July 18, 1977, February 6,1978 and February 25, 1981, 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 confonnity 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 requirer.ients have been satisfied.
DESIG;IATED ORIGINAL Certified By i klY^tsh Qui o'
-2
- 2. A'ccordingly, the license i Specifications as indicated i s amended by changes to the Tech i amendment, and paragraph 3 3 of F No. OPR-27 is hereby amend d n the attachment to this licen n cal acility Operat e
e to read as follows:ing License se B.
The Technical Specificatio A and B, as revised through Ans contained in Appe hereby incorporated in th e license.ent No. 66, ndices mendm operate the fa Specifications.cility in accordance with thThe licensee shall are 3.
This license amendment is e Technical effective as of the date of its issuance FOR THE NUCLEAR REGULATOR
)
OMMISSION i
- g. (u.u
(' *. (L
/
i f' i
obert A. Clark, Chief u*
Division of LicensingOperating Re
Attachment:
Changes to the Technical Specifications Date of Issuance:
June 25, 1982 r
I
%s
% *~m
+_,N_.
~~%...
l
- k
" 7.Nw-
~
ATTACHMENT TO LICENSE AMENDMENTS AMENDMENT NO. 61 TO FACILITY OPERATING LICENSE NO. OPR-24 AMENDMENT NO. 66 TO FACILITY OPERATING LICENSE NO. OPR-27 DOCKET NOS. 50-266 AND 50-301 Revise Appendix A as follows:
Remove pages Insert Pages 15.4.4-1 15.4.4-1 15.4.4-2 15.4.4-2 15.4.4-3 15.4.4-3 15.4.4-4 15.4.4-4 15.4.4-5 15.4.4-5 15.4.4-6 15.4.4-6 15.4.4-6a 15.4.4-6b l
i
(
15.4.4 CONTAINMENT TESTS Applicability Applies to containment leakage and structural integrity.
Objective To verify that potential leakage from the containment and the pre-stressing ten-don loads are maintained within acceptable values.
Specification I.
Type A periodic Integrated Leakage Rate Test A.
Test 1.
The Type A periodic in-service integrated leakage rate test shall be perfonned at intervals specified in I-C below at an initial pressure Pt at or above 30 psig (50% of design pres-~
sure P )-
a 2.
The test duration shall not be less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> unless test experiences of at least 2 prior tests provide evidence of the adequacy of shorter test duration.
Test accuracy shall be verified by supplementary means such as measuring the quantity of air required to return to the starting pressure (P ) or by t
imposing a known leak rate to demonstrate the validity of mea surements.
3.
Closure of the containment isolation valves for the purpose of l
the test shall be accomplished by the means provided for nor-mal operation of the valves without preliminary exercises or adj ustment.
Repairs of maloperating or leaking valves shall l
hn"it 15.4.4-1 Amendment No. 61 AnerAment."o.
66
l be made as necessary.
Description of valve closure malfunc-tion or valve leakage that requires corrective action before the test shall be included in the Test Report.
4.
Leak repairs, if required during the integrated leakage test, shall be preceded and followed by local leakaqe rate measure-ments.
A description of the repairs and the leakage rates measured prior to and after the repairs shall be included in the Test Report.
B.
Acceptance Criteria 1.
The governing criteria for acceptance of peak pressure tests is that the maximum allowable leakage (L ) shall not exceed 0.40 a
weight percent per day of containment atmosphere at 60 psig (P }
a which is the design pressure.
2.
The allowable in-service leakage rate (L ) at the reduced test t
pressure (P ) shall not exceed L (Ltm/ lam), except if Ltm/ lam t
a is greater than 0.7, Lt shall be equal to La(P /P )l/2 Where:
t a L is the maximum allowable leakage rate at pressure P for the a
a preoperational tests; the subscript m refers to values of the leakage measured during initial preoperational tests; and the sub-scripts a and t refer to tests at accident pressure and reduced test pressure respectively.
3.
The measured leakage rata (Ltm) for in-service tests shall not exceed 0.75 L. as determined under B-1 above.
t Unit 1 15.4.4-2 Amendment No. 61 JMA2
- 1hr.vamrvao m sa
10 l
l 4.
The supplementary test described in I.A.2 is acceptable, pro-vided the difference between the supplemental test data and the Type "A" test data is within 0.25 L.
If results are not t
within 0.25 L. the reason shall be determined, corrective t
action taken, and a successful supplemental test performed.
5.
If repairs are necessary to meet the acceptance criteria, the inteqrated leakage rate test need not be repeated provided local measured reductions in leakages achieved by repairs re-duce the overall measured integrated leakage rate to a value not in excess of 0.75 L.
Local leakage measurements taken to t
effect repairs to meet the acceptance criteria shall be taken at a test pressure P for full pressure tests and P for re-a t
duced pressure tests.
C.
Frequency 1.
Integrated leakage rate tests shall be performed as follows:
After the initial preoperational leakage rate test, two in-tegrated leakage rate tests shall be performed at approxi -
mately equal intervals between each major shutdown for in-service inspection to be performed at 10 year intervals.
In addition, an integrated test shall be performed at each 10 year interval, coincidinq with the in-se'rvice inspection shut-down.
The test shall coincide with a shutdown for major fuel reloading.
2.
If two consecutive Type "A" tests fail to meet the applicable Unit 1 Amendment No. 61 15.4.4-3 Unit 2 knendment No. 66
i acceptance criteria in Section 1.B above, a Type "A" test shall be performed at each plant shutdown for refueling, or approxi-mately every 18 months, whichever occurs first.
The acceler-ated test schedule shall continue until two consecutive Type "A" tests pass, after which time the retest schedule in I.C.1 may be resumed.
D.
Report of Test Results 1.
Each Type "A leakage rate test will be the subject of a summary technical report, which will include summaries of Type "B" and "C" tests (Items II and III below) that were performed since the last Type "A" test.
II.
Type "B" Tests A Type "B" test neasures leakage across individual and/or portions of pres-sure containing or leakage-limiting boundaries of primary reactor contain-ment penetrations as defined in II.A.3.
A.
Test l
1.
Type "B" tests shall be performed at intervals specified in II.D below and at a pressure of not less than P -
a 2.
Acceptable methods of testing are halogen leak detection, pres-sure decay and fluid flow using air or nitrogen. Another method may be used if it can be shown to have equivalent sensitivity.
r i
Unit 1 15.4.4-4 Amendment No. 61 Unit 2 Amendment No. 66
j 3.
The local leakage shall be measured for each of the following components:
Containment penetrations that employ resilient seals, a.
gaskets or sealant compounds, pipino penetrations fitted with expansion bellows and electrical penetrations fitted with flexible metal seal assemblies, b.
Airlock and equipment door seals, including operating mechanism and penetrations with resilient seals which are part of the containment boundary in the airlock structure.
I c.
Fuel transfer tube flange seal.
d.
Other containment components which require leak repair in order to meet the acceptance criterion for any intearated leakage rate test.
B.
Acceptance Criterion The total leakage from items II.A.3 and III.A.3 shall not exceed 0.6 La-1.
If at any time it is determined that 0.6 La is exceeded, repairs shall be initiated immediately.
After repair, a retest to con-firm conformance to the acceptance criterion of II.B is re-quired.
2.
If repairs are not completed and conformance to the acceptance criterion of II.B is not demonstrated within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, the re-actor shall be taken to cold shutdown conditions until repairs are effected and the local leakaqe meets this acceptance criterion.
15.4.4-5 Amendment No. 61 Unit 1 Amendment No. 66 Unit 2
C.
Test Frequency 1.
Individual penetrations shall be tested during each shutdown for major fuel reloading except as specified in a and b below.
In no case shall the interval be greater than two years.
a.
The containment equipment hatch flange seals and the fuel transfer tube flange seals shall be tested at each shutdown for major fuel reloading or after each time used, if that be sooner.
b.
The personnel air lock door seals shall be tested at 6 month intervals, except when the air locks are not opened during the interval.
In that case the test is to be performed after each opening, except that no test interval is to exceed 12 months.
III. Type "C" Tests A Type "C" test measures the leakage across an individual valve or_ across a group of valves used to isolate an individual penetration through the primary reactor containment as defined in III. A.3.
A.
Test 1.
Type "C" tests shall be performed at intervals specified in III.D below and at a pressure of not less than P - a 2.
Acceptable methods of testing are by local pressurization and the methods described in II.A.2 above.
The pressure shall be applied in the same direction as that when the valve would be required to perform its safety function, unless it can be determined that the results from the tests for a pressure ap-plied in a different direction will provide equivalent or more conservative results.
Each valve to be tested shall be closed by normal operation and without any preliminary exercising or adj us tments.
Unit 1 15.4.4-6 Amendment No. 61 m
m
ro il 3.
Local leakage shall be measured for containment isolation valves that:
Provide a direct connection between the inside and outside a.
atmospheres of the primary reactor cc"ainment under norval operation.
b.
Are required to close automatically upon receipt of a con-tainment isolation signal.
Are required to operate intermittently under post-accident c.
conditions.
B.
Acceptance Criterion The total leakage from items II.A.3 and III.A.3 shall not exceed 0.6 La-C.
Corrective Action i.
If at any time it is determined that 0.6 L is exceeded, repairs a
shall be initiated immediately.
After repair, a retest to con-firm conformance to the acceptance criterion of III.B is re-quired.
2.
If repairs are not completed and conformance to the acceptance criterion of III.B is not demonstrated within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, the re-actor shall be taken to cold shutdown conditions until repairs i
are effectedand the local leakage meets this acceptance criterion.
D.
Test Frecuency 1.
The above tests of the isolation valves shall be conducted during each shutdown for major fuel reloadina but in no case at inter-vals greater than two years.
Unit 1 Unit 2 15.4. 4-6a Amendment No. 61
_% m m
s IV.
Residual Heat Removal System A.
Test (a) The portion of the Residual Heat Removal System, except as 1.
specified in (b), that is outside the containment shall be tested either by use in normal operation or hydrostatically tested at 350 psig at the interval specified in IV.D below.
(b) Piping from the containment sump to the residual heat re-moval pump suction isolation valve shall be pressure tested at no less than 50 psig at the interva.1 specified in IV.D below.
l Unit 1 15.4.4-6b Unit 2 Amendment No. 61 Amendment No. 66
_