ML20087C582
| ML20087C582 | |
| Person / Time | |
|---|---|
| Site: | Waterford  (NPF-38-A-110) |
| Issue date: | 08/03/1995 |
| From: | Chandu Patel NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20087C584 | List: |
| References | |
| NUDOCS 9508090257 | |
| Download: ML20087C582 (9) | |
Text
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NUCLEAR REGULATORY COMMISSION 2
WASHfNOTON, D.C. 2055!M001
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ENTERGY OPERATIONS. INC.
DOCKET NO. 50-382 WATERFORD STEAM ELECTRIC STATION. UNIT 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.110 License No. NPF-38 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Entergy Operations, Inc. (the licensee) dated May 12, 1995, 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 and regulations of the Commission; C.
There is reasonable assurance (1) that the activities authorized by this amendment car 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 requirements have been satisfied.
I 9500090257 950003 "
DR ADOCK 0 382
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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-38 is hereby amended to read as follows:
(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No.110, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license.
The licensee shall operate.the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of its date of issuance to be implemented within 60 days.
FOR THE NUCLEAR REGULATORY COMMISSION i
[j4v4(4 bbd Chandu P. Patel, Project Manager j
Project Directorate IV-1 Division of Reactor Projects Ill/IV Office of Nuclear Reactor Regulation i
Attachment:
Changes to the Technical 1
Specifications Date of Issuance:
August 3, 1995 i
a ATTACHMENT TO LICENSE AMENDMENT NO.110 TO FACILITY OPERATING LICENSE NO. NPF-38 DOCKET NO. 50-382 Replace the following pages of the Appendix A Technical Specifications with the attached pages. The revised pages are identified by Amendment number and contain vertical lines indicating the areas of change.
The corresponding overleaf pages are also provided to maintain document completeness.
REMOVE PAGES INSERT PAGES 3/4 6-2 3/4 6-2 3/4 6-3 3/4 6-3 3/4 6-4 3/4 6-4 8 3/4 6-1 B 3/4 6-1
3/4. 6 CONTAINMENT SYSTEMS 3/4. 6.1 PRIMARY CONTAINMENT CONTAINMENT INTEGRITY t
L1MITIN3 CONDITION FOR OPERATION 3.6.1.1 Primary CONTAINMENT INTEGRITY shall be maintained.
APPLICABILITY:
MODES 1, 2, 3, and 4.
ACTION:
I Without primary CONTAINMENT INTEGRITY, restore CONTAINMENT INTEGRITY within I hour or be in 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 t
SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SUFVEIL!ANCE REQUIREMENTS 4.6.1.1 Primary CONTAINMENT INTEGRITY shall be demonstrated:
At least once per 31 days by verifying that all penetrations
- not a.
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, exce,pt for valves that are open under acministrative control as permitted by Specification 3.6.3.
b.
By verifying that each containment air lock is in compliance with the requirements of Specification 3.6.1.3.
Af ter each closing of each penetration sub. ject to Type B testing, c.
except containment air locks, if opened following a Type A or B test, by leak rate testing the seal with gas at P,, 44 psig, and verifying that when the measured leakage rate for these seals is added to the leakage rates detereined pursuant to Specifica-tien 4.6.1.2d for all other Type B and C penetrations, the combined leakage rate is less than or equal to 0.60 L,.
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"Except valves, blind flanges, and deactivated automatic valves which are located inside the containment and are locked, sealed or otherwise secured in the tiesed position. These penetrations shall be verified closed during each COLD SKUTDOWN except that such verification need net be perfomed more often than once per 92 days.
WATERFDRD - UNIT 3 3/4 6-1 AMEhDMENT NO. 75
CONTAINMENT SYSTEMS CONTAINMENT LEAKAGE LIMITING CONDITION FOR OPERATION 3.6.1.2 Containment leakage rates shall be limited to:
a.
An overall integrated leakage rate of:
1.
Less than or equal to L 0
containment air per 24 b,our.50 percent by weight of the s at P,, 44 psig, or 2.
Less than or equal to L 0
containment air per 24 b,our.25 percent by weight of the s at a reduced pressure of P,
1 22 psig, b.
A combined leakage rate of less than or equal to 0.60 L for all penetrationsandvalvessubjecttoTypeBandCtestswben pressurized to P,.
A combined bypass leakage rate of less than or equal to 0.06 L, for c.
all penetrations that are secondary containment bypass leakage paths when pressurized to P,.
APPLICABIllTY:
MODES 1, 2, 3, and 4.
ACTION:
With either (a) the measured overall integrated containment leakage rate exceeding 0.75 L, or 0.75 L'a,tions and valves subject to Types B and C tests as applicable, or (b) with the measured combined leakage rate for all penetr exceeding 0.60 L,, or (c) with the combined bypass leakage rate exceeding 0.06 L,, restore the overall integrated leakage rate to less than or equal to 0.75 L, or less than or equal to 0.75 L,, as applicable, and the combined leakage rate for all penetrations and valves subject to Type B and C tests to less than or equal to 0.60 L, and the bypass leakage rate to less than or equal to 0.06 L, prior to inc,reasing the Reactor Coolant System temperature above 200*F.
SURVEitLANCE REQUIREMENTS 4.6.1.2 The containment leakage rates shall be cemonstrated as follows:
WATERFORD - UNIT 3 3/4 6-2 AMENDMENT NO. 75,85,110
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-CONTAINMENT' SYSTEMS i
- SdRVEfttANCEREQUIREMENTS'(Ccotinued) l Type A tests shall be conducted in accordance with the schedule and a.
criteria specified in 10 CFR 50, Appendix J, as modified by. approved j
exemptions.
i, b.
Type B and C tests shall be conducted with gas at. P, 44 psig, at..
intervals no greater than 24 months except for tests involving:
t 1.
Air locks, 2.
Purge supply and exhaust isolation valves with resilient-
'l material seals.
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WATERFORD.- UNIT 3 3/4 6-3 AMENDMENT N0. 4 86,110 -
7 L
CONTAINMENT SYSTEMS SURVElllANCE RE001REMENTS (Continued)-
c.
Purge supply and exhaust isolation valves with resilient material l
seals shall be tested and demonstrated OPERABLE per Surveillance Requirement.4.6.1.7.2.
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f.
Thecombinedbypassleakagerateshallbe'determinedtobelessthanl l
or equal to 0.06 L, by applicable Type B and C tests at least once per 24 months except for penetrations which are not individually
-l testable; penetrations not individually testable shall be determined to have no detectable leakage when tested with soap bubbles while the containment is pressurized to P,, 44 psig, during each Type A i
test.
Air locks shall be tested and demonstrated OPERABLE per Surveillance l e.
Requirement 4.6.1.3.
f.
The provisions of Specification 4.0.2 are not applicable.
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I WATERFORD - UNIT 3 3/4 6-4 AMENDMENT NO. 4r85,110 J
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3/4.6 CONTAINMENT SYSTEMS BASES 3/4.6.1 PRIMARY 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 t
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 Part 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 safety analyses at the peak accident pressure, P. As an added conservatism, the measured overall integrated leakage rate,is further limited to less than or equal to 0.75 L or less than or equal to 0.75 L as applicable during performance of the periodic tests to account for,,possible degradation of the containment leakage barriers between leakage tests.
The surveillance requirements for measuring leakage rates are consistent with the requirements of 10 CFR 50, Appendix J and performed in accordance with the methods and provisions of ANSI N45.4-1972.
Secondary containment bypass leakage paths previously, Table 3.6-1, have been incorporated into plant procedure UNT-005.026.
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 provides assurance that the overall air lock leakage will not become excessive due to seal damage during the intervals between air lock leakage tests.
WATERFORD - UNIT 3 B 3/4 6-1 AMENDMENT NO. 75 85,110 7
CONTAfNMENT 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 0.65 psid, (2) the containment peak pressure does not exceed the design pressure of 44 psig during either LOCA or steam line break conditions, and (3) the minimum pressure of the ECCS performance analysis (BTP CSB $1) is satisfied.
The maximum peak pressure expected to be obtained from an MSLA event is 42.3 psig.
The limit for initial positive containment pressure of +27 inches water (approximately 1.0 psig) will limit the total pressure to less than 44 psig which is less than the design pressure and is consistent with the safety analyses.
The limit for initial positive containment pressure includes a correction of 1.20 inches water for possible instrument error and an addi-tional 6.8 inches water for conservatism.
The limit of 14.375 psia for initial negative containment pressure ensures that the minimum containment pressure is consistent with the ECCS performance analysis ensuring core reflood under LOCA conditions.
3/4.6.1.5 AIR TEwpERATURE.
The limitation on containment average air temperature ensures that the containment peat air temperature does not exceed the design temperature of 269.3*F curing LCCA concitions and 413.5'F during MSLB conditions and is consistent with the safety analyses.
3 /4. 6.1. 6 CONTAINWENT VESSEL STRUCTURAL INTEGRITY This limitation ensures that the structural integrity of the containment 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 R&Kibus pressure of 43.76 psig in the event of a main steam line breat accident.
A visual inspection in conjunction with lype A leatage test is sufficient to demonstrate this capability.
3/a.6.1.7 CONTAINMENT VENTILATION SYSTEM The use of the containment purge valves is restricted to 90 hours0.00104 days <br />0.025 hours <br />1.488095e-4 weeks <br />3.4245e-5 months <br /> per year in accordance with Standard Review Plan 6.2.4 for plants with the Safety Evaluation Report for the Construction License issued prior to July 1, 1975.
The purge valves have been modified to limit the opening to approximctely 52' to ensure the valves will close during a LOCA or MSL8; and therefore, the SITE BOUNDARY doses are maintained within the guidelines of 10 CFR Part 100.
The purge valves, as modified, comply with all provisions of BTP CSB 6-4 except for the recommended size of the purge line for systems to be used during plant operation.
WATERFORD - UNIT 3 8 3/4 6-2 Amendment No. 27
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