ML20247C663
| ML20247C663 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 07/18/1989 |
| From: | Yandell L Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20247C669 | List: |
| References | |
| NUDOCS 8907240406 | |
| Download: ML20247C663 (6) | |
Text
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UNITED STATES g
NLCLEAR REGULATORY COMMISSION n
W ASHINGToN, D. C. 20556 '
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CONSUMERS POWER COMPANY PALISADES PLANT r
DOCKET NO. 50-255 AMENDMENT,TO PROVISIONAL OPERATING LICENSE i
Amendment No.126, License No. DPR-20 1.'
The Nuclear Regulatory Commission (the Commission) has found that:
"A.
The application for amendment by Consumers Power Company (the licensee) dated March 3, 1982 as supplemented by letters dated August 29, 1984, March 21, 1988, and April 20 and May 4, 1989, 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 tad 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 pgblic; 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 commen defense and security or to the health and safety of the public: and E.
The issuance of this amendment is in accordance with la CFR Part 51 of the Commission's regulations and all applicable. requirements have been satisfied.
2.
Accordingly, the licease is amended by changes to +he Technical Specifications as indicated in the attachment to this license amendment and Paragraph 3.B. of Provisional Operating License No. DPR-20 is hereby amended to read as follows:
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 126, are hereby incorporated '
in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
s907240406 890718 POR ADOCK 05000255 p
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3.
This license amendaient is effective as of the date of its issuance and shall be implemented not later than July 24, 1989.
FOR THE NUCLEAR REGULATORY COMMISSION Lawrence A. Yandell, Acting Director Project Directorate III-1 Division of Reactor Projects - III, IV, V
& Special Projects
Attachment:
Changes to the Technica, Specifications Date of Issuance: July 18, 1989
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eiS CONTAINMENT TESTS (Contd) 3 I
(2)
If any periodic integrated leak rate test fails to meet
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the acceptance criteria, the test schedule applicable to i
subsequent integrated leak rate tests will be reviewed and approved by the Commission.
e.
Report of Test Results Each integrated leak rate test will be the subject of a summary technical report which will include summaries of local 1
leak detection tests and leak test of the recirculation heat remova? systems.
4.5.2 LocalLe(';DetectionTests a.
Test (1) Local leak rate tests shall be performed at a pressure of not less than 55 psig.
(2) Local leak rate tests for checking air lock door seals
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within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> of each door opening shall be performed
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at a pressure of not less than 10 psig.
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(3) Acceptable methods of testing are halogen gas detection,
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soap bubble, pressure deci.y. or equivalent.
(4) The local leak. rate shall be measured for each of the
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following components:
(a) Containment penetrations that employ resilient seal gaskets, sealant compounds, or bellows.
(b) Air lock and equipment door seals.
(c) Fuel transfer tube.
(d) Isolation valves on the testable fluid systems' l
lines penetrating the containment.
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(e) Other containment components which require leak repair in order to meet the acceptance criterion for any integrated leak rate test.
b.
Acceptance Criteria (1) The total leakage from all penetrations and. isolation
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valves shall not exceed 0.60 La.
j (2) The leakage for an air lock door seal test shall not
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exceed 0.023 La.
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c.
Corrective Action (1)
If at any time it is determined that 0.60 La is exceeded, repairs shall be initiated immediately.
4-27 Amendment No. U, 126 1
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1 4.5 CONTAINMENT TESTS (Continued)
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4.5.2 Local Leak Detection Tests (Continued)
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It repairs are not completed and conformance to the acceptance criterion'of 4.5.2.b(1) is not demonstrated
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within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />,.the Plant shall be placed in-at-least
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hot shutdown within the n' ext 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in at least
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cold shutdown within the following 30. hours.
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(2)
If at any time it.1s determined that total containment
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leakage exceeds La, within one hour action shall be
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initiated to bring the Plant to hot shutdown within the
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next six (6) hours and cold shutdown with % the following
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'l thirty (30) hours.
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(3). If air lock door seal leakage is greater than 0.023 La,
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repairs shall be initiated immediately to restore the
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door to less than specification.4.5.2.b(2).
In the' event
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repairs cannot be completed within 7 days, the Plant
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shall-be brought to a hot shatdown. condition within the
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next six (6) hours and cold' shutdown within the
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following thirty (30) hours.
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if air lock door seal leakage results in one (1) door..
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causing total containment leakage to exceed 0.60 La, the
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do
- shall be declared inoperable and the remaining
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rpe.able door shall be immediately locked closed aad
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tested within four '(4) hours.
As long as the remaining
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door is found to be operable, the provisions of 4.5.2.c(2)
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do'not apply.
Repairs shall be initiated immediately to
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establish conformance with specification 4.5.2.b(1).
In
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the event conformance to this specification cannot be.
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established within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> the Plant'shall be brought'to
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a' hot shutdown within the next 6' hours and cold shutdown-
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within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
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d.
Test Frequency (1) Individual penetrations and containment isolation valves shall.b-leak rate tested at a frequency of at least every six months prior to the first postoperational-
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integrated leak rate test and at a frequency ^of at least every refueling thereafter, not exceeding (a two-year interval, except as specified in'(a) and b)below
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(a) The containment equipment haten and the fuel transfer i
. tube shall be tested at each refueling shutdown or i
after each time used, it that be sooner.
t 4-28 H #dd NW 7 Amendment No 71, 126' l
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-i 4.5 CONTAINMENT TESTS (Continued)
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4.5.2 Local Leak Detection Tests (Continued)
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(b) A full air lock penetration test shall be. performed-
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.at six-month intervals. During.the period between
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l the six-month. tests when' containment integrity is.
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required, a reduced pressure' test'for the door seals-
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or a full air, lock penetration test shall be performed../
within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> after either each air' lock l door.
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opening or the;first ot~a series of openings.
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(2) Each three months.the isolation' valves must be stroked to i
the position required to fulfill their1 safety function unless'it is established that such operation-is not practical' during plant operation. The latter valves shall be full-stroked during each cold shutdown.
4.5.3 Recirculation Heat Removal Systems a.
Test (1) The' portion of the shutdown cooling; system that is.
outside the containment shall be tested either by use in normal operation or hydrostatically' tested' at 255 psig at.the interval specitted in 6.15.
(2) Piping from valves CV-3029'and CV-3030 to the' discharge l
of the safety injection purrps and containment spray pumps shall_ be hydrostatically tested at no less than 100 psig at the interval.specified'in 6.15.
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Amendment No. 77, 126 9
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4.5 ONTAINMENT TESTS (Cont'd)
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an important part of the structural integrity of the containment j
is maintained.
The basis for specification of a total leakage rate ot 0.60 La I
from penetrations and isolation valves is specified to provide assurance that the integrated leak rate would remain within the i
specified limits during the intervals between integrated leak I
rata tests. This value allows for possible deterioration in the j
intervals between tests.
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The basis for specification of an airlock door seal leakage rate
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j of 0.023 La is to provide assurance that the failure of a single
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l airlock door will not result in the total containment leakage
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exceeding 0.6 La. The seven (7) day LCO specified for exceeding
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the airlock door leakage limit is acceptable since it requires
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that the total containment le skage limit is not exceeded.
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The limiting leakage rates frsm the shutdown cooling system are
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judgment values based primarily on assuring that the components I
could operate without mechanical failure for a period on the i
order of 200 days after a DBA.
The test pressure (270 psig) j achieved either by normal system operation or by hydrostatically 1
testing gives an adequate margin over the highest pressure within
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the system after a DBA. Similarly, the hydrostatic test pressure
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for the return lines from the containment to the shutdown cooling 4
system (100 psig) gives an adequate margin over the hignest 1
pressure withP ;he lines after a DBA.(5)
I A shutdown cooling system leakage of 1/5 gpm will limit off-site exposures due to leakage to insignificant levels relative to those calculated for leakage directly from the containment in the DBA.
The engineered safeguards room ventilation system is equippd with isolation valves which close upon a high radiation signal from a local radiation detector. These monitors shall be set at 5
2.2 x 10 c m, which is well below the ex>ected level following a loss-of-coo ant accident (LOCA), even wit 1out clad failure. The 1/5 gpm leak rate is sufficiently high to permit prompt detection and to allow for reasonable leakage through the pump seals and valve packings, and yet small enough to be readily handled by the sumps and radioactive waste system. Leakage to the engineered safeguards room sumps will be returned to the containment. clean water receiver following a LOCA, via the equipment drain tank and l
pumps. Additional makeup water to the containment sump inventory can be readily accommodated via the charging pumps from either the SIRW tank or the concentrated boric acid storage tanks.
4-35 Amendment No. IZ, JI, 709, 126
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