ML17285B300
| ML17285B300 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 05/31/1990 |
| From: | Larkins J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17285B301 | List: |
| References | |
| NUDOCS 9006070077 | |
| Download: ML17285B300 (8) | |
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UNITEDSTATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 WASHINGTON PUBLIC POWER SUPPLY SYSTEM DOCKET NO. 50-397 NUCLEAR PROJECT NO.
2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 85 License No.
NPF-21 l.
The Nuclear Regulatory Commission (the Commission or the NRC) has found that:
A.
The application for amendment filed by the Washington Public Power Supply System (the licensee),
dated February 5, 1990 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 author-ized 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 regula-tions 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.
900+07007 500397 PDR AGOCK 050 DC P
P
2.
Accordingly, the license is amended by changes to the Technical Speci-fications as indicated in the attachment to this license amendment and paragraph 2.C.(2) of Facility Operating License No. NPF-21 is hereby amended to read as follows:
(2)
Technical S ecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 85
, and the Environmental Protection Plan contained in Appendix B, are hereby incor-porated in the license.
The licensee shall operate the
,facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This amendment is effective as of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION John T. Larkins, Acting Director Project Directorate V
Division of Reactor Projects - III, IV, V and Special Projects Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
May 31, 1990
ATTACHMENT TO LICENSE AMENDMENT NO.
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 vertical lines indicating the areas of change.
Also to be replaced are the following overleaf pages.
AMENDMENT PAGES 3/4 8-8 3/4 8-9 OVERLEAF PAGES 3/4 8-7 3/4 8-10
/1 1
t
ELECTRICAL POWER SYST S
SURVEILLANCE RE UIREMENTS Continued 2.
Performing a pressure test of those portions of the diesel fuel oil system designed to Section III, subsection ND of the ASME Code in accordance with ASME Code Section XI Article IWD-5000.
4.8. 1. 1.3
~Re orts - All diesel generator failures, valid or nonvalid, shall be reported to the Commission pursuant to Specification 6.9.1.
Reports of diesel generator failures shall include the ihformation recommended in Regulatory Position C.3.b of Regulatory Guide 1.108, Revision 1, August 1977.
If the number of failures in the last 100 valid tests, on a per diesel generator basis, is greater than or equal to 7, the report shall be supplemented to include the additional information recommended in Regulatory Position C.3.b of Regulatory Guide 1.108, Revision 1, August 1977.
WASHINGTON NUCLEAR - UNIT 2 3/4 8"8 Amendment No. 85
ELECTRICAL POWER SYSTEMS SURVEILLANCE RE UIREMENTS Continued 9.
Verifying that the auto-connected loads to each diesel generator do not exceed the 2000-hour rating of 4650 kW for DG-1 and DG-2 and 2850 kW for DG"3.
10.
Verifying th'e diesel generator's capability to:
a)
Synchronize with the offsite power source while the generator is 'loaded with its emergency loads upon a simulated restoration of offsite power, b}
Transfer its loads to the offsite power source, and c)
Be restored to its standby status.
11.
Verifying that with the diesel generator operating in a test mode and connected to its bus, a simulated ECCS actuation signal overrides the test mode by (1) returning the diesel generator to standby operation, and (2} automatically energizes the emergency loads with offsite power.
12.
Verifying that the automatic load sequence timer is OPERABLE with the interval between each load block within a 10K of its design interval for DG-1 and DG-2.
13.
Verifying that the following diesel generator lockout features prevent diesel generator starting only when required:
a)
Maintenance lock-out key lock switch.
b)
Emergency stop.
f.
At least once per 10 years or after any modifications which could affect diesel generator interdependence by starting all three dies'el generators simultaneously, during shutdown, and verifying that all three diesel generators accelerate to at least 900 rpm (> 60 Hz) in less than or equal to 10 seconds.
g.
At least once per 10 years by:
l.
Draining each fuel oil storage tank, removing the accumulated
- sediment, and cleaning the tank using a sodium hypochlorite or equivalent solution, and WASHINGTON NUCLEAR - UNIT 2 3/4 8-7
TABLE 4.8.1.1.2"1 DIESEL GENERATOR TEST SCHEDULE Number of Failures in Number of Failures Last 20 Valid Tests" or Last 100 Valid Tests" Test Fre uenc
> 5 At least once per 31 days At least once per 7 days "Criteria for determining number of failures and number of valid tests shall be in accordance with Regulatory Position C.2.e of Regulatory Guide 1.108, Revision 1, August 1977, where the number of tests and failures is determined on a per diesel generator basis.
For the purposes of this test schedule, only valid tests conducted after the OL issuance date shall be included in the computation of the "last 100 valid tests."
Entry into this test schedule shall be made at the 31 day test frequency.
Mith the exception of the semiannual fast start, no starting time requirements are required to meet the valid test requirements of 'Regulatory Guide 1.108.
""Once this test frequency is required, it shall be maintained until seven consecutive failure free valid tests have been performed and the number of failures in the last 20 demands has been reduced to one.
MASHINGTON NUCLEAR - UNIT 2 3/4 8"9 Amendment No. 8~
ELECTRICAL POWER SYSTEMS A.C.
SOURCES -
SHUTDOWN LIMITING CONDITION FOR OPERATION 3.8.1.2 As a minimum, the following A.C. electrical power sources shall be OPERABLE:
a ~
b.
One circuit between the offsite transmission network and the onsite Class 1E distribution system, and Diesel generator 1 or 2 (DG-1 or DG-2), and diesel generator 3
(DG-3) when the HPCS system is required to be OPERABLE, with each diesel generator having:
l.
Day fuel tanks containing a minimum of 1400 gallons of fuel.
2.
A fuel storage system containing a minimum of 53,000 gallons of fuel for DG-1 and DG"2, and 33,000 gallons of fuel for DG-3.
3.
A fuel transfer pump.
APPLICABILITY:
OPERATIONAL CONDITIONS 4, 5, and ".
ACTION:
a o b.
C.
With less than the offsite circuits and/or DG-1 or DG-2 of the above required A.C. electrical power sources OPERABLE, suspend CORE ALTERATIONS, handling of irradiated fuel in the secondary containment, operations with a potential for draining the reactor vessel and crane operations over the spent fuel storage pool when fuel assemblies are stored therein.
In addition, in OPERATIONAL CONDITION 5, with the water level less than 22 feet above the reactor pressure vessel
- flange, immediately initiate corrective action to restore the required power sources to OPERABLE status as soon as practical.
With DG-3 of the above required A.C. electrical power sources inoperable, restore the inoperable diesel generator 1C to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or declare the HPCS system inoperable and take the ACTION required by Specification 3.5.2 and 3.5.3 The provisions of Specification 3.0. 3 are not applicable.
SURVEILLANCE RE UIREMENTS 4.8. 1.2 At least the above required A.C. electrical power sources shall be demonstrated OPERABLE per Surveillance Requirements 4.8. 1. l. 1, 4.8. l.1.2, and 4.8. 1. 1.3, except for the requirement of 4.8. l. 1.2.a.5.
"When handling irradiated fuel in the secondary containment.
WASHINGTON NUCLEAR " UNIT 2 3/4 8-10