ML17285A276
| ML17285A276 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 02/22/1989 |
| From: | Knighton G Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17285A277 | List: |
| References | |
| NUDOCS 8903030291 | |
| Download: ML17285A276 (8) | |
Text
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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.
65 License No.
NPF-21 1.
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 November 19, 1987 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.
89030302
, 0500039 890222 PDR ADO K PDC P
2.
Accordingly, the license is amended by changes to the Techni ca 1 Specifications 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.
65, 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 amendment is effective as of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
Attachment:
Changes to the Technical Specifications George
. Knighto Director Projec Directora e
V Division of Reactor Projects - III, IV, V and Special Projects Date of Issuance:
February 22, 1989
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ENCLOSURE TO LICENSE AMENDMENT NO.
65 FACILITY OPERATING LICENSE NO. NPF-21 DOCKET NO. 50-397 Replace the following page of the Appendix "A" Technical Specifications with the enclosed page.
The revised page is identified by Amendment number and contains a vertical line indicating the area of change.
Also to be replaced is the overIeaf page.
AMENDMENT PAGE 3/4 3-12 OVERLEAF PAGE 3/4 3-11
TABLE 3.3.2-1 ISOLATION ACTUATION INSTRUMENTATION VALVE GROUPS MINIMUM OPERATED BY OPERABLE CHANNELS TRIP FUNCTION SIGNAL PER TRIP SYSTEM a) 1.
PRIMARY CONTAINMENT ISOLATION APPLICABLE OPERATIONAL CONDITION ACTION a.
Reactor Vessel Mater Level 1)
Low, Level 3
2)
Low Low, Level 2
Drywell Pressure - High Main Steam Line 1)
Radiation - High b.
C.
d.
e.
f.
g.
2)
Pressure - Low 3)
Flow - High Main Steam Line Tunnel Temperature - High Main Steam Line Tunnel h Temperature - High Condenser Vacuum - Low Manual Initiation 2.
SECONDARY CONTAINMENT ISOLATION 5(g) 1, 2, 4
4, 5(b)(g) 1(c) 2(c) 1 1
1 1
1 2
5(b)(g) 2 2
2 2(d) 2 2
2/group 1/group 1/group 1
2 3
1 2
3 1
2 3
1,2,3 1
1 2
3 1
2 3
1 2
3
]
2A 3*
1, 2, 3
20 20 21 22 23 21 21 21 21 24 24 24 20 aO b.
C.
d.
Reactor Building Vent Exhaust Plenum Radiation - High Drywell Pressure - High Reactor Vessel Mater Level - Low Low, Level 2 Manual Initiation 3(b)(e) 3(b)(e) 3(b)(e) 3(b) 3(b) 2 1/group 1/group 1, 2, 3, and **
25 1, 2, 3
25 1, 2, 3, and ¹ 25 24 24 O
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INSTRUMENTATION 0 SURVEILLANCE RE UIREMENTS 4.3.2.1 Each isolation 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 4.3.2.1-1.
4.3.2.2 LOGIC SYSTEM FUNCTIONAL TESTS and simulated automatic operation of all channels shall be performed at least once per 18 months.
4.3.2.3 The ISOLATION SYSTEM RESPONSE TIME of each isolation trip function shown in Table 3.3.2-3 shall be demonstrated to be within its 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 isolation trip system.
WASHINGTON NUCLEAR - UNIT 2 3/4 3-11
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