ML17279B039
| ML17279B039 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 05/05/1988 |
| From: | Knighton G Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17279B040 | List: |
| References | |
| TAC-67082, NUDOCS 8805200139 | |
| Download: ML17279B039 (9) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 WASHINGTON PUBLIC POWER SUPPLY SYSTEM DOCKET NO. 50-397 WPPSS NUCLEAR PROJECT NO.
2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
License No.
DPR-21 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Washington Public Power Supply System (the Supply System, also the licensee),
dated February 5, 1988 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's 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 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 Commission's regulations set forth in 10 CFR Chapter I; 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.
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.
DPR-21 is hereby amended to read as follows:
8805200139 880505 PDR ADOCH; 05000397 P
P3)R
(2) Technical S ecifications The Technical Specifications contained in Appendix A, as revised through Amendment No.
56, 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.
FOR THE NUCLEAR REGULATORY COMMISSION
Attachment:
Changes to the Technical Specifications Date of Issuance:
May 5, 1988 George
. Knight
, Director Projec Directo te V
Division of Reactor Projects - III, IV, V and Special Projects
May 5, 1988 ENCLOSURE TO LICENSE AMENDMENT NO.
56 FACILITY OPERATING LICENSE NO. NPF-21 DOCKET NO. 50-397 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages.
The revised pages are identified by Amendment number and contain a vertical line indicating the area of change.
REMOVE 3/4 6-11 3/4 6-12 INSERT 3/4 6-11 3/4 6-12
E
'ONTAINMENT SYSTEMS DRYWELL AND SUPPRESSION CHAMBER PURGE SYSTEM LIMITING CONDITION FOR OPERATION 3.6. 1.8 The drywell and suppression chamber purge system may be in operation with the drywell and/or suppression chamber purge supply and exhaust butterfly isolation valves open for inerting, deinerting, or pressure control, provided that each butterfly valve is blocked so as not to open more than 70'.
PURGING through the Standby Gas Treatment System shall be restricted to less than or equal to 90 hours0.00104 days <br />0.025 hours <br />1.488095e-4 weeks <br />3.4245e-5 months <br /> per 365 days (SEE NOTE 1).
APPLICABILITY:
OPERATIONAL CONDITIONS 1, 2, and 3.
ACTION:
a.
With a drywell and/or suppression chamber purge supply and/or exhaust butterfly isolation valve open for other than inerting, deinerting, or pressure control, or not blocked to less than or equal to 70'pen, close the butterfly valve(s) within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
b.
With a drywell and suppression chamber purge supply and/or exhaust isolation valve(s) with resilient material seals having a measured leakage rate exceeding the limit of Surveillance Requirement 4.6. 1.8.2, restore the. inoperable valve(s) to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
SURVEILLANCE RE UIREMENTS 4.6. 1.8. 1 When being opened, the drywell and suppression chamber purge supply and exhaust butterfly isolation valves shall be verified to be blocked so as to open to less than or equal to 70~ open, unless so verified within the previ ous 31 days.
4.6. 1.8.2 At least once per 6 months, on a STAGGERED TEST BASIS, each 24-and 30-inch drywell and suppression chamber purge supply and exhaust isolation valve with resilient material shall be demonstrated OPERABLE by verifying that the measured leakage is:
a.
Less than or..equal to 0.05 L
per valve test or, a
b.
Greater than 4. 6. 1. 8. 2. a. provided that:
- 1) the valves are secured closed and maintenance performed at the next plant cold shutdown to reduce the leakage to within 4. 6. l. 8. 2. a; 2) the leakage added to the previously determined total for all valves and penetrations subject to Type B and C tests per LCO 3/4.6. 1.2 shall be less than 0.6 L
a'.
In the event the valves are to be operated, and 4.6. 1.8.2.a.
has been
- exceeded, a leakage test must be performed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> following operation.
to ensure compliance with 0 6 La WASHINGTON NUCLEAR - UNIT 2 3/4 6-11 AMENDMENT NO.
56
CONTAINMENT SYSTEMS SURVEILLANCE RE UIREMENTS Continued
- 4. 6. 1.8.3 The cumulative time that the drywell and suppression chamber purge system has been in operation PURGING through the Standby Gas Treatment System shall be verified to be less than or equal to 90 hours0.00104 days <br />0.025 hours <br />1.488095e-4 weeks <br />3.4245e-5 months <br /> per 365 days prior to use in this mode of operation (SEE NOTE 1).
NOTE 1:
For the period of time ending April 10, 1988 this value shall be 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> per 365 days.
WASHINGTON NUCLEAR - UNIT 2 3/4 6-12 AMENDMENT NO.
56