ML17290A947
| ML17290A947 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 01/31/1994 |
| From: | Adensam E Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17290A948 | List: |
| References | |
| NUDOCS 9402070341 | |
| Download: ML17290A947 (8) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON. D.C. 20555-0001 W
S NGTO U
OWR U
ENDMENT 0
C T
OP RATING LICENSE Amendment No.
i2O License No. NPF-21 The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by the Washington Public Power Supply System (licensee) dated January 13,
- 1994, 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 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 Commission's regulations; 2.
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.
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:
940207034i 94013i PDR ADOCK-.05000397 P
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'(2) ech ical S ec'fic t ons d
v pnme ta otectio lan The Technical Specifications contained in Appendix A, as revised through Amendment No.
12O 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.
This amendment is effective from the date of issuance to be implemented within 7 days.
FOR THE NUCLEAR REGULATORY COMNISSION Pg-d.
Elinor G. Adensam, Assistant Director for Regions IV 5 V Reactors Division of Reactor Projects III/IV/V Office of =Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
january 31, 1994
AC ND E
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1 Replace the following page of the Appendix A Technical Specifications with the enclosed page.
The revised page is identified by amendment number and contains vertical lines indicating the areas of change.
The corresponding overleaf page is also provided to maintain document completeness.
RKDMV 3/4 3-25 SERT 3/4 3-25
~331333 NT
.3 MERGENCY CORE COO ING SYSTEM CTU T ON INS UM TATIO LIMITING CONDITION FOR OPERATION 3.3.3 The emergency core cooling system (ECCS) actuation instrumentation channels shown in Table 3.3.3-1 shall be OPERABLE with their trip setpoints set consistent with the values shown in the Trip Setpoint column of Table 3.3.3-2 and with EMERGENCY CORE COOLING SYSTEM RESPONSE TIME as shown in Table 3.3.3-3.
~APP 33 I ITT:
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I I 31 3.3.3-1.
~CT ON:
a.
With an ECCS actuation instrumentation channel trip setpoint less conservative than the value shown in the Allowable Values column of Table 3.3.3-2, declare the channel inoperable until the channel is restored to OPERABLE status with its trip setpoint adjusted consistent with the Trip Setpoint value.
b.
With one or more ECCS actuation instrumentation channels inoperable, within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> take the ACTION required by Table 3.3.3-1.
c.
With either ADS trip system "A" or "B" inoperable, restore the inoperable trip system to OPERABLE status:
- 2. Within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
Otherwise, 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 reduce reactor steam dome pressure to less than or equal to 128 psig 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 4.3.3. 1 Each ECCS actuation instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL FUNCTIONAL TEST, and CHANNEL CALIBRATION operations for the OPERATIONAL CONDITIONS and at the frequencies shown in Table 4.3.3. 1-1.
4.3.3.2 LOGIC SYSTEM FUNCTIONAL TESTS and simulated automatic oper ation of all channels shall be performed at least once per 18 months.
- 4.3.3.3 The ECCS
RESPONSE
TIME of each ECCS trip function shown in, Table 3.3.3-3 shall be demonstrated to be within the limit at least once per 18 months.
Each test shall include at least one channel per trip system such that all channels are tested at least once every N times 18 months where N is the total number of redundant channels in a specific ECCS trip system.
- Response time testing of the Low Pressure Systems as specified in Technical Specification Table 3.3.3-3, items I and 2, is not a requirement for OPERABILITY until the startup following the next COLD SHUTDOWN, but no later than the startup following the Spring 1994 Refueling Outage.
WASHINGTON NUCLEAR UNIT 2 3/4 3-25 Amendment No. ~i20
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