ML20011E526
| ML20011E526 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 01/31/1990 |
| From: | Hannon J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20011E527 | List: |
| References | |
| NUDOCS 9002160006 | |
| Download: ML20011E526 (7) | |
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I**iane UNITED STATES '
-8 NUCLEAR REGULATORY COMMISSION n
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t-WASHINGTON, D. C. 20565
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TOLEDO EDISON COMPANY AND THE CLEVELAND ELECTRIC ILLUMINATING COMPANY DOCKET NO. 50-346 4
DAVIS-BESSE NUCLEAR POWER STATION, UNIT NO. I AMENDMENT TO FACILITY OPERATING LICENSE i
i Anendment No.146 License No. NPF-3 1.
The Nuclear Pegulatory Cormission (the Comission) has found that:
A.
The application for amendment by the Toledo Edison Cernpany and The Cleveland Electric Illuminating Company (the licensees) dated March 7, l
1988 complies with the standards and requirements of the Atonic Energy Act of 1954, as amended (the Act), and the Coimission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in confornity with the application, the provisions of the Act, and the rules and regulations of the~
Cor.nission; C.
There is. reasonable assurance (1) that the activities authorized by
-l 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 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 Ccomission'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. HPF-3 is hereby amended to read as follows:
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(a) Technical Specifications F
The Technical Specifications contained in Appendix A, as revised through Amendment No.-146, are hereby incorporated in the license.
The Toledo Edison Company shall operate the facility in accordance with the Technical Specifications.
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3.
This license amendment is effective as of its date of issuance and shall l
be implemented not later than 45 days after issuance.
FOR THE NUCLEAR REGULATORY COMMISSION l r f 7 l.
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/v'johnN.Hannon, Director Project Directorate III-3 Division of Reactor Projects - III, IV, V, & Special Projects Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
January 31, 1990 1
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ATTACHMENT TO LICENSE AMENDMENT NO. 146 FACILITY OPERATING LICENSE NO. NPF-3 DOCKET NO. 50-346 P.eplace the following pages of the Appendix "A" Technical Specifications y the attached pages. The revised pages are identified by amendment number contain vertical lines indicating the area of change. The correspondin' overleaf pages are also provided to maintain document completeness.
r Remove insert 3/4 6-2 3/4 6-2 B 3/4 6-1 B 3/4 6-1 e
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4 3/4.6 CONTAINMENT SYSTEMS 3/4. 6.1 PRIMARY CONTAINMENT t
CONTAINMENT INTEGRITY LIMITING CONDITION FOR OPERATION 3.6.1.1' Primary CONTAINMENT INTEGRITY shall be maintained.
APPLICABILITY:
MODES 1, 2, 3 and 4.
ACTION:
Without primary CONTAINMENT INTEGRITY, restore CONTAINMENT INTEGRITY within one hour or be ia 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:
a.
At least once per 31 days by verifying that:
1.
All penetrations
- not capable cf 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 closeo 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.
CAVIS-BESSE, UNIT 1 3/4 6-1 i
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CONTAINMENT SYSTEMS CONTAINMENT LEAKAGE LIMITING CONDITION FOR OPERATION y
3.6.1.2 Containment leakage rates shall be limited to:
lj a.
An overall integrated leakage rate of 1 a0:50 percent by L
l 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 P,, 38 psig.
b.
A combined leakage rate of < 0.60 L, for all penetrations and a
valves subject to Type B anI C tests, when pressurized to Pa-c.
A combined leakage rate of < 0.015 La for all penetrations identified in Table 3.6-1 as secondary containment bypass leakage paths, when pressurized to P,.
d.
A single penetration leakage rate of 1 0.15 L for the contain-
-l mentpurgeandexhaustisolationvalvespecia$ test.
- APPLICABILITY: MODES 1, 2, 3 and 4.
I ACTION:
a.
With either (a) the measured overall integrated containment leakage rate exceeding 0.75 La (b) with the measured combined l
1eakage rate for all penetrations and valves subject to Type B and C tests exceeding 0.60 L, or (c) with the combined bypass leakage rate exceeding 0.015 La, restore the leakage rate (s) to J
within-the limit (s) prior to increasing the Reactor Coolant System temperature above 200'F.
b.
With a single containment purge and exhaust isolation valve penetration having leakage rate exceeding.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 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 />.
l SURVEILLANCE REQUIREMENTS
- 4. 6.1. 2 The containment leakage rates shall be demonstrated at the i
following test schedule and shall be determined in conformance with the criteria specified in Appendix J of 10 CFR 50 using the methods and l
provisions of ANSI N45.4 - 1972:
a.
Three Type A tests (0verall Integrated Containment Leakage Rate) shall be conducted at 40 + 10 month intervals during shutdown at P, 38 psig, during each TO year service period.
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DAVIS-BESSE, UNIT 1 3/4 6-2 Amendment No. 90', 146
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3/4.6 COSTAINMENT SYSTEMS BASES 3/4.6.1 PRIt%RY CONTAINMENT 3/4.6.1.1 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 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 assumed in the s fety analyses at the peak accident pressure of 38 psig, P, As an a
added conservatism, the mecsured overall integrated leakage rate is further limited to < 0.75 La,dation of the containment leakage barriers during performance of the periodic tests to account for possible degra between leakage tests.
The surveillance testing for measuring leakage rates are consistent with the requirements of 10 CFR Part 50, Appendix J with the following exemption.
The third test of.each Type A testing set need not be conducted when the plant is shutdown for the 10-year plant inservice inspections.
The operational readiness of the vessel is considered proven by the ILRT, and in accordance with license requirements, when completed per the 401 10 months frequency.
The special test for the containment purge and exhaust isolation 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 locks are required to meet the restrictions on CONTAINMENT 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.
DAVIS-BESSE, UNIT 1 B 3/4 6-1 Amendment No. 90,146
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CONTAINMENT SYSTEMS BASES 3/4.6.1.4 INTERNAL PRESSURE The limitations on 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 of 40 psig during LOCA conditions.
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 total pressure to 38 psig which is less than the design pressure and is consistent with the safetv analyses.
3/4.6.1.5 AIR TEMPERATURE L
The limitations on containment average air temperature ensure that l
the overall containment average air ten.perature does not exceed the initial temperature condition assumed in the accident analysis for a LOCA.
3/4.6.1.6 CONTAINMENT VESSEL STRUCTURAL INTEGRITY This limitation ensures that the structural integrity of the contain-ment steel vessel will be maintained comparable to the original design 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 leakage tests is sufficient to demonstrate this capability.
3/4.6.1.7 CONTAINMENT VENTILATION SYSTEM The limitation on use of the Containment Purge 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 that a direct open path would exist from the containment atmosphere to the outside atmosphere and consequently reduces the probability that an accident dose would exceed 10 CFR 100 guideline values in the event of a LOCA occurring coincident with purge system operation. The use of this system is therefore restricted to non-routine usage not to exceed 90 l
hours in any consecutive 365 day period which is equivalent to approximately 1% of the total possible yearly unit operating time.
3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS 3/4.6.2.1 CONTAINMENT SPRAY SYSTEM The OPERABILITY 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 lower containment DAVIS-BESSE, UNIT 1 B 3/4 6-2 Amendment No.135