ML20029A366
| ML20029A366 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 02/11/1991 |
| From: | Marsh L Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20029A367 | List: |
| References | |
| NUDOCS 9102210020 | |
| Download: ML20029A366 (11) | |
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION s
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CONSUMERS POWER COMPANY n
PALISADES PLANT j
f DOCKET NO. 50-255 AMENDMENT TO PROVISIONAL-OPERATING LICENSE i
Amendment No. 135 License No. DPR-20 1.
The Nuclear Regulatory Commission (the Comission) has found that:
A.
The applications for amendment by(change 1), Septeinber 20 Consumers Power Company (the licensee)datedAugust 21, 1990
, 1990, and as amended on November 20, 1990 (change 2), and October 4, 1990(change 3)complieswiththestandardsandreq)uirementsof 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 t5e rules and regulations of the Commission; C.
There is reasonable assurance (1) that the activities authorized
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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 irsbance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
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 Provisional Operating License No. DPR-20 is hereby amended to read as follows:
9102210o20 910211 PDR ADOCK 05000255 P
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2 Techhical-Specifications The Tech'nical Specifications contained in Appendices A-and_B,-
as revised through Amendment No.135
- 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 its date of issuance..
FOR THE NUCLEAR REGULATORY COMMISSION
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L. B. Marsh, Director Project Directorate 111-1 Division of Reactor. Projects III/IV/V Office of Nuclear Reactor Regulation
Attachment:
Changes-to the Technical Specifications Date of.lssuance:' February 11,1991 I
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ATTACHMENT TO LICENSE AMEN 0 MENT N0_._131
,s PROVISIONAL _OPERAT_ING LICENSE NO._DPR-20 DOCKET NO. 50-255 Revise Appendix A Technical S)ecifications by removing the pages identified below and inserting the attacled pages. The revised pages are identified by the amendment number and contain marginal lines indicating the area of change.
REMOVE INSERT 3-40b 3-40b
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3-40e 3-40e 4-25 4-25 4-26 4-26 4-27 4-27 4-33 4-33 4-34 4-34 5-2 5-2
TABLE 3.6.1 CONTAIMENT PENETRATIONS AND VALVES SYSTEM MAME AND VALVE PEN NUMBER-SERVICE LINE-SIZE ID NO REMARKS 1A PURGE AIR EXHAUST CV-1805 Auto isolation valve; (8")
CV-1806.
required closure time - 25 seconds IC PURGE AIR EXHAUST-CV-1807 Auto isolation valve; (8")
CV-1808 required closure-time = 25 seconds 5
S/G (E-50A)
CV-0767.
Auto isolation valve; BLOWDOWN CV-0771 required c1'osure (4")
time = 25 seconds 6
S/G (E-508)
CV-0768 Auto isolation valve; BLOWDOWN
.CV-0770 required closure (4")*
time'- 25 seconds 11 CONDENSATE TO
'CV-0939 Auto isolation valve; SHIELD COOLING CK-CD401 required closure SURGE TANK-time - 25 seconds (1 4")
14 COMPONENT COOLING CV-0910 Auto isolation valve; WATER IN (10")
CK-CC0910 required closure time - 25 seconds 15 COMPONENT COOLING CV-0911 Auto isolation valve; WATER OUT (10")
CV-0940 required closure time = 25 seconds 16 S/G (E-50A)
CV-0739 Auto isolation valve; RECIRCULATION (4")*
required closure time - 25 seconds
- Pene'tration line size; isolation valves are 2-inch.
3-4Gb l
i Amendment No. //S.135
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' TABLE 3.6.1 CONTAINMENT PENETRATIONS AND VALVES SYSTEM MAME AND' VALVE PEN NUMBER' SERVICE LINE SIZE ID NO REMARKS
'47 PRIMARY SYSTEM CV-1002 Auto isolation valve; DRAIN TANK PUMP CV-1007 required closure SUCTION (4")
time - 25 seconds 49 CLEAN WASTE CV-1038 Auto isolation valve; RECEIVER TANK-CV-1036 required closure CIRCULATION PUMP time - 25 seconds SUCTION (3")
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' CONTAINMENT SUMP CV-Il03 Auto isolation valve; DRAIN TO DIRTY WASTE CV-Il04 required closure TANK (4")
time - 25 seconds 55 S/G (E-508)
CV-0738 Auto isolation valve; RECIRCULATION (4"),
required closure time - 25 seconds 67 CLEAN WASTE CV-1037 Auto isolation valve; RECEIVER TANK PUMP CK-CRW408 required closure RECIRC (3")
time - 25 seconds 68 AIR SUPPLY TO CV-1813 Auto isolation valve; AIR ROOM (12")-
CV-1814 required closure time - 25 seconds 69 CLEAN WASTE-CV-1045 Auto isolation valve; RECEIVER TANK PUMP CV-1044 required closure-SUCTION (4")
time - 25 seconds
- Penetration line size; isolation valves are 2-inch.
I 3-40e Amendment No. J/5,135 J
4.5 CONTAU.? TNT TTSTC Applicabilftv Applies te containe.ent leakage and structural integrity.
Objective To verify that potential leakaFe from the containeent and the pre-stressing tendon loads are maintained within specifi.d values.
Specifications 4.5.1 Integrated Leakare Rate Tests A surveillance test prograr. for the containment overall integrated
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leakage rate shall meet the 10 CTR 50, Appendix J. Type A test requirements or approved exer.ptionr.
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d Amendment No.12 Change No. 16 Fe b. 11, 1975 4-25 Amendment No 135
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u Amendment No.12 Change No. 16 February 11, 1975 Amendment No. 135 4-26
P 4.5.0 Local Leak Detection Tests a.
Test (1) Local leak rate tests shall be performed at a pressure of rot less than 55 psig.
(2) Loce) leck rate testa fer checking air lock door seals within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> of each door openine shall be performed at a pressure of not less than 10 psir.
(3) Acceptable methods of testing are halogen gas detection, soap bubble, pressure decav, or ecu1 valent.
(4) The local leak rate shall be measured for each of the following corponents:
(a) Containment penetrations that employ resilient seal gaskets, sealant corpounds, or bellows.
(bi Air lock and eculpment door seals.
( c 's fuel transfer tube.
(d)
Isolation valves on the testable fluid systees' linea peretrating the containment.
(e) Other contain:ent components which recuire leak repair in order to reet the acceptance criterion for any integrated leak rate test.
b.
A g gance Criteria (1) The total 1cakepe fron all penetrations and isolation valves shall not exceed 0.60 La.
(2) The leakage for an air lock door seal test shall not exceed 0.023 La.
c.
Corrective Action (1)
If at any tire it is determined that 0.60 La is exceede? repairs shall be initiated immediately.
L-27 Amendrent b' o. 17. 12f.135 Y
4.5 CONTAINMENT TESTS (Cont'd)
Basis The containment is designed fo'; av eccident pressure of 55 psig.II)
While the reactor is operating..ae internal environment of the contaitment vill be air at approximately atmospheric pressure and a temperature of about 104'T. With these initial conditions, following a LOCA, the temperature of the steam-air mixture at the peak accident pressure of 55 psig is 283'T.
prior to initial operation, the containment was strength-tested at 63 psig and then leak rate tested. The design objective of this-preoperational leak rate test was established as 0.1% by weight per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at 55 psig. This leakage rate is consistent with the construction of the containment.I2) which is eouipped with independent leak-testable penetrations and contains channels over all unaccessible containment liner velds, which were independently leak-tested during construction.
Accident analyses have been performed on the basis of a leakage rate of 0.1% by weight per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. With this leakage rate and with a reactor power level of 2530 Mk't, the potential public exposure vould be below 10 CTP 100 guideline values in the event of the Maximum Eypothetical Accident.I3)
The performance of a periodic integrated leak rate test during plant life provides a current assessment of potential leakage from the containment in case of an accident that would pressurize the interior of the containment. In order to provide a realistic appraisal of the integrity of the containment under accident _ conditions, this periodic
-leak rate test is to be performed without preliminary leak detection surveys or leak repairs and containment isolation valves are to be closed in the normal manner.
This normal manner is a coincident two-of-four high radiation or two-of-four high containment pressure signale which vill close all containment isolation valves not recuired for engineered safety features except the component cooling lines' valves which are closed by CHp only. -The control system is designed on a two-channel (right f
and left) concept with redundancy and physical separation. Each l
channel is capable of initiating containment isolation.I')
l 4-33 Amendment No. 109. 135
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4 24.5 CONTAINMENT TESTS (Cont'd)
The Type A test reoutrements including pretest test methods, test pressure, acceptance criteria, and reporting reoutrements are in accordance with 10 CFR 50, Appendix J, reouirements or approved exemptions.
The frecuency of the periodic integrated leak rate test is keyed to the refueling schedule for the reactor because these tests can best be performed during refueling shutdowns. The specified frecuency is as specifled in 10 CFR Part 50, Appendix J vhich is based on three major considerations. First is the low probability of leaks in.the liner because of (a) the test'of the leak tightness of the welds during erection; (b) conformance of the complete containment to a low leak rate at 55 psig during preoperational testing which is consistent with 0.1% leakage at design basis accident (DBA) conditions: and (c) absence of any significant stresses it. the liner during reactor operation.
Second is the more frecuent testing, at the full accident pressure, of those portions of the containment envelope that are most likely to develop leaks during reactor operation (penetrations and isolation valves) and the low value (0.60L,) of the total leakage that is specified as acceptable from penetrations and isolation valves. Third is the tendon stress surveillance program which provides assurance that 4-34 Amendment No. 109,135
.5.2 CONTAINWENT DESICN FEATURES (Cont'd) 5.2.2 Penetrations a.
A11~ penetrations through the steel lined concrete structure for electrical conductors, pipe, ducts, air locks and doors are of the double barrier design.
b.
The automatically actuated centainment isolation valves are designed to close upon high radiation or high pressure in the containment structure. No single component failure in the actuation system will prevent the isolation valves from functioning as designed.
5.2.3 containment Structure Cooline Systems a.
The containment air cooling system includes four separate self-contained units which cool the containment air during normal operation and limit the pressure rise in the event of a design accident.
Three units, each with a cooling water flow of 4875 s
gpa with an inlet temperature of 75'r, will remove 229 x lo Beu/hr of heat, b.
The containment spray system is capable of removing 233 x 108 Beu/hr (two pumps) from the containment atmosphere at 283'T by spraying the water from the 270,000 gallon SIRV tank.
Recirculation of spray water from the containment sump:through heat exchangers into the containment atmosphere is also provided.
Under this mode of operation, the heat removal capability is 167 x 10' Beu/hr -based upon 4000 gpa of component cooling water flow with 114'T inlet temperature through the heat exchanger and 1420 gpm of spray water flow at 283'F inlet temperature.
5.3 NUCLEAR STEAM SUPPLY SYSTEM (NSSS) 5.3.1 Primary Coolant System Desien Pressure and Temocrature The primary coolant system is designed, and shall be maintained:
a.
-In accordance with the Code requirements specified in Section 4.2 of the FSAR with allowance for normal degradation pursuant to the surveillance requirements, b.
For a pressure of 2500 psia, c.
For a temperature of 650*F, except the pressurizer, which shall be 700'F, and d.
With a volume of approximately 10,900 cubic feet.
5-2 Amendment No.135
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