ML20138C651

Amend 90 to License NPF-3,incorporating Requirements for Special Leak Testing of Containment Purge Isolation Valves to Determine If Excessive Degradation of Valve Seats Occurred

ML20138C651
Person / Time
Site:	Davis Besse
Issue date:	11/27/1985
From:	Stolz J Office of Nuclear Reactor Regulation
To:	Toledo Edison Co, Cleveland Electric Illuminating Co
Shared Package
ML20138C658	List: ML20138C651 ML20138C675
References
TAC 57219, NPF-03-A-090 NUDOCS 8512130064
Download: ML20138C651 (9)

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TOLEDO EDISON COMPANY AND THE CLEVELAND ELECTRIC ILLUMINATING COMPANY DOCKET NO. 50-346 DAVIS-BESSE NUCLEAR POWER STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 90 License No. NPT-3 1.

The Nuclear Regulatory Comission (the Comission) has found that:

A.

The application for amendment by the Toledo Edison Company and The Cleveland Electric illuminating Company (the licensees) dated August. 18, 1983, as modified November 20, 1934, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules anc' 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 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 Comission's regulations; D.

The issuance of this amendment will not be inimical to the comon 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 Comission'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 2.C.(2) of Facility Operating License No. NPF-3 is hereby amended to read as follows:

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ib 2-Technical Specifications The Technical Specifications contained in Appendices A and B as revised through Amendment No. 90,are hereby incorporated in the license. The Toledo Edison Company 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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J hn F. Stolz, Direct PWR Project Directorate #6 divisionofPWRLicensing-B

Attachment:

i Changes to the Technical Specifications Date of Issuance: November 27, 1985 t

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O ATTACHMENT TO LICENSE AMENDMENT NO.90 FACILITY OPERATING LICENSE NO. NPF-3 DOCKET NO. 50-346 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change. The corresponding overleaf pages are also provided to maintain document completeness.

Remove Insert 3/4 6-2 3/4 6-2 3/4 6-3 3/4 6-3 3/4 6-4 3/4 6-4 B 3/4 6-1 B 3/4 6-1 t-13 i

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3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT CONTAINMENT INTEGRITY LIMITING CONDITION FOR OPERATION 3.6.1.1 Primary CONTAINMENT INTEGRITY shall be maintained.

APPLICABILITf: MODES 1, 2, 3 and 4.

ACTION:

Withcut primary CONTAINMENT INTEGRITY, restore CONTAINMENT INTEGRITY within one hour 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 /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

SURVEILLANCE REQUIREMENTS 4.6.1.1 Primary CONTAINMENT INTEGRITY shall be demonstrated:

t a.

At least once per 31 days by verifying that:

1.

All penetrations

• not capable of being closed by OPERABLE containment automatic isolation valves and required to be closed during accident conditions are closed by valves, blind flanges, or deactivated automatic valves secured in their positions, except as provided in Table 3.6-2 of Specification 3.6.3.1, and 2.

All equipment hatches are closed and sealed.

b.

By verifying that each containment air lock is OPERABLE per Specification 3.6.1.3.

• Except valves, blind flanges, and deactivated automatic valves which are located inside the containment and are locked, sealed, or otherwise secured in the closed position. These penetrations shall be verified closed during each COLD SHUTDOWN except that verification of these penetrations being closed need not be performed more often than once per 92 days.

DAVIS-BESSE, UNIT 1 3/4 6-1 9

CONTAINMENT SYSTEMS 1

CONTAINMENT LEAKAGE LIMITING CONDITION POR OPERATION 3.6.1.2 Containment leakage rates shall be limited to:

An overall integrated leakage rate of 1 L, 0.50 percent by a.

weightofthecontainmentairper24hourIatP,,38psig.

valvessubjecttoTypeBaalCtestI,forallpenetrationsand A combined leakage rate of < 0.60 L b.

when pressurised to P,.

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A combined leakage rate of i 0.015 L for all penetrations identified in Table 3.6-1 as secondaFy containment bypass leakage paths, when pressurised to P,.

d.

A single penetration leakage rate of 5 0.15 L for the containment purgeandexhaustisolationvalvespecialtest.

APPLICABILITY: NODES 1, 2, 3 and 4.

ACTION:

a.

With either (a) the acasured overall integrated containment leakagerateforallpenetration(b)withthemeasuredcombined leakage rate exceeding 0.75 L s and valves subject to Type B

, or (c) with the combined bypass and C tests exceeding 0.60 L,L, restore the leakage rate (s) to t

leakage rate exceeding 0.015 j

within the limit (s) prior to i$ creasing the Reactor Coolant System temperature above 200'T.

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b.

With a single containment purge and exhaust isolation volve penetraties having leakage rate escoeding 0.15 L ; restore the leakage rate to within limits in 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be la at least NOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

I SURVEILIANCE REQUIRDENTS 4.6.1.2 The containment leakage rates shall be demonstrated at the following test schedule and shall be determined in conformance with the criteriaspecifieginAppendizJof10CFR50meingthemethodsand provisions of ANSI N45.4 - 1972:

Three Type A tests (Overall Integrated Containment Leakage Rate) a.

shall be conducted at 40 + 10 month intervals during shutdown at P, 34 pois, during each to year service period. The third test ofeachsetshallbeconductedduringtheshutdownforthe10 year plaat inservice inspection.

DAVIS-BESSE, UNIT 1 3/4 6-2 Amendment No. 90

6 CONTAINMDfT SYSTDfS StitVEILIANCE REQUIRDENTS (Continued) b.

If any periodic Type A test fails to meet.75 L the test scheduleforsubsequentTypeAtestsshallber0v,iewedand approved by the Commission. If two consecutive Type A tests fail to meet.75 L, a Type A test shall be performed at ". east every 18 months until two ceasecutive Type A testa meet.75 L at which time the above test sekedule asy be resumed.

The accuracy of each Type A test shall be verified by a supplemental c.

test which:

1.

Confirms the accursey of the Type A test by verifying that the difference between supplemental and Type A test data is within 0.25 L,.

2.

Ras a duration sufficient to establish accurately the change in leakage between the Type A test and the supplemental test.

3.

Requires the quantity of gas injected into the containment or bled from the containment during the supplemental test to be equivalent to at least 25 percent of the totsi measured leakage rate at P,, 38 psig.

d.

Type B and C tests shall be conducted with gas at P, 38 peig, at intervals no greater than 24 months except for testI involving:

1.

Air locks, 2.

Penetrations using continuous leakage monitoring systems, and 3.

Yalves pressurized with fluid from a seal system.

The combined bypass leakage rate shall be determined to be 1

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< 0.015 L by applicable Type B and C tests at least once every 24 months,except for penetrations which are not individually testable; penettstices not individually testable shall be determined to have ao detectable leakage when tested with soap bubbles while the containment is pressurized to P,, 34 pais, during each Type A test.

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Air locks shall be tested and demonstrated OPDtABLE per Surveillance Requirement 4.6.1.3.

DAVIS-BESSE, UNIT 1 3/4 6-3 Amendeent No. 90

l l CONTAINMENT SYSTEMS SURVEII. LANCE REQUIREMENTS (Continued) 3 14akage from isolation valves that are sealed with fluid from a seal system asy be excluded, subject to the provisions of Appendix J,Section III.C.3, when determinias the combined leakage rate previded the sesi system and valves are pressurised to at least 1.10 P, 41.8 peig, and the seal system especity is adequate to maintain Iystes pressure for at least 30 days.

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Type B tests for penetratiosa amployias a costiamous leakage monitoring systes shall be conducted at P,, 38 peig, et intervals no greater than once per 3 years.

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Each time the containment purge and exhaust isolation valves are opened, a special test shall be performed withia 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> after valve closure or prior to entering mode 4 from mode 5, whichever i

is later. The special test is esedseted by pressurising the piping section including one valve inside and one valve outside the con-tainment to a pressure greater or equal to 20 pois. The leakage rate per penetration shall not exceed 0.15 L,.

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The special test as defined la surveillance Requirement 4.6.1.2.1 shall be performed for the containment purge and isolation valves when the plaat has been la any combination of modes 3, 4, 5 or 6 for more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> provided that the tests required by Sur-veillance Requirements 4.6.1.2.1 or 4.6.1.2.d have not been performed in the previous 6 months.

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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 measurseest system.

1.

The provisions of Specifiestion 4.0.2. are not applicable.

DAVIS-BESSE, UNIT 1 3/4 6-4 Amendment No. 90 l

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l 3/4.6 CONTAINMENT SYSTEMS BASES 3/4.6.1 PRIMARY CONTAINMENT 3/4.6.1.1 CONTAIMENT 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 safety analyses.

This restriction, in conjunction with the leakage rate limitation, will limit the site boundary radiation doses to within the limits of 10 CFR 100 during accident conditions.

3/4.6.1.2 CONTAINMENT LEAKAGE The limitations on containment leakage rates ensure that the total containment leakage volume will not exceed the value asstmed in the safety analyses at the peak accident pressure of 38 psig, P. As an added conservatism, the measured overall integrated leakage,ra'te is further limited to < 0.75 L, during performance of the periodic tests to account for possible deg,radation of the containment leakage barriers between leakage tests.

The surveillance testing for measuring leakage rates are consistent with the requirements of Appendix "J" of 10 CFR 50.

The special test for the containment purge and exhaust isolation t

valves is intended to detect gross degradation of seals on the valve seats. The special test is performed in addition to the Appendix J requirements.

3/4.6.1.3 CONTAINMENT AIR LOCKS The limitations on closure and leak rate for the containment air

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locks are required to meet the restrictions on CONTAI MENT INTEGRITY and containment leak rate. Surveillance testing of the air lock seals provide assurance that the overall air lock leakage will not become excessive due to_ seal damage during the intervals between air lock leakage tests.

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DMIS.BESSE, UNIT 1 B 3/4 6-1 Amendment No. 90

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CONTAI! MENT SYSTEMS BASES-l 3/4.6.1.4 INTERNAL PRESSURE 1

The limitations en containment internal pressure ensure that 1) the containment structure is prevented from exceeding its design negative pressure differential with respect to the annulus atmosphere of 0.5 psi and 2) the containment peak pressure does not exceed the design pressure 4

of 40 psig dur 4g LOCA conditions.

l The maximum peak pressure obtained from a LOCA event is 37 psig.

The limit of 1 psig for initial positive containment pressure will limit the tot 91 pressure to 38 psig which is less than the design pressure and is consistent with the safety analyses.

3/4.6.1.5 AIR TEMPERATURE l

The limitations on containment average air temperature ensure than the overall containment average air temperature does not exceed the' initial temperature condition assumed in the accident analysis for 4 LOCA.

I 3/4.6.1.6 CONTAINENT VESSEL STRUCTURAL INTEGRITY This limitation ensures that the structural integrity of the con'tain-ment steel vessel will be maintained comparable to the original design 4

standards for the life of the facility. Structural integrity is required to ensure that the vessel will withstand the maximum pressure of 38 psig in the event of a LOCA. A visual inspection in conjunction with Type A l

1eakage tests is sufficient to demonstrate this capability.

i 3/4.6.1.7 CONTA!! MENT VENTILATION SYSTEM The limitation on use of the Containment PJrge and Exhaust System limits the time this system may be in operation with the reactor coolant system temperature above 200*F. This restriction minimizes the time

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l that a direct open path would exist from the containment atmosphere to the outside atmosphere and consequently reduces the probability that an accident dose unuld murand 10 CFR 100 guideline values in the event of a LOCA occuring coincident with purge system operation. The use of this system is therefore restricted to non-routine usage not to exceed 90 hours0.00104 days <br />0.025 hours <br />1.488095e-4 weeks <br />3.4245e-5 months <br /> in any consecutive 365 day period thich is equivalent to approximately 15 of the total possible yearly unit operating time.

l 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS I

3/4.6.2.1 CONTAlleENT SPRAY SYSTEM I

The OPERASILITY of the containment spray system ensures that contain-ment depressurization and cooling capability will be available in the event of a LOCA. The pressure reduction and resultant louer contalement i

i DAVIS-BESSE, UNIT 1 B 3/4 6-2 i

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