ML17278A485
| ML17278A485 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 11/20/1985 |
| From: | Butler W Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17278A486 | List: |
| References | |
| TAC-59236, NUDOCS 8511260618 | |
| Download: ML17278A485 (9) | |
Text
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+0 4 ~**4 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 WASHINGTON PUBLIC POWER SUPPLY SYSTEY.
DOCKET NO. 50-397 WPPSS NUCLEAR PROJECT NO.
2 AMENDMENT TO FACILITY OPERATING LICENSE License No. NPF-21 Amendment No.
18 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 Supply System, also the licensee) dated July 9, 1985, 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 CFP, Chapter I; B.
The facility will operate in conformity with the application as
- amended, 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 CFP, Chapter I; D.
The issuance of this amendment will not be inimical to the common defense and security or 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, Facility Operating License No. NPF-21 is amended to revise the Technical Specifications as indicated in the attachment to this amendment and paragraph 2.C.(2) of Facility Operating License 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. 18, 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.
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This amendment is effective as of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION l4'i+i~ p$~pZ by ~
klalter R. Butler, Chief Licensing Branch No.
2 Division of Licensing
Enclosure:
Changes to Technical Specifications Date of Issuance:
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ATTACHMENT TO LICENSE ANENDYiENT NO.
18 FCILI Y
R GLICENS N.
-1 D CKET NO. 50-39 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 areas of change.
REViOVE 3/4 3-35 6-7 INSERT 3/4 3-35 6-7
TABLE 4.3.3. 1-1 (Continued)
EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION SURVEILLANCE RE UIREMENTS TRIP FUNCTION B.
DIVISION 2 TRIP SYSTEM 1.
RHR B AND C LPCI MODE CHANNEL CHECK CHANNEL FUNCTIONAL TEST CHANNEL CALIBRATION OPERATIONAL CONDITIONS FOR WHICH SURVEILLANCE RE UIRED a 0 b.
C.
d.
e.
Reactor Vessel Water Level-Low Low Low, Level l Drywell Pressure
- High Reactor Vessel Pressure-Low (LPCI Permissive)
LPCI Pump B Start Time Delay Relay LPCI Pump Discharge Flow-Low (Minimum Fl ow)
Manual Initiation S
N.A.
N.A.
N.A.
N.A.
N.A.
R N.A.
1, 2, 3, 4*, 5*
1, 2, 3, 4*, 5*
3 4*
5*
3 4*
5*
. O 2.
AUTOMATIC DEPRESSURIZATION SYSTEM TRIP SYSTEM 'IB"¹ a.
Reactor Vessel Water Level-Low Low Low, Level 1
b.
ADS Timer c.
'ow, Level 3 (Permissive) d.
LPCI Pump 8 and C Discharge Pressure-High (Pump Running)
Manual Initiation Inhibit Switch S
N.A.
N.A.
N.A.
N.A.
R N.A.
N.A.
1,2,3 1, 2, 3
3., 2, 3
1, 2, 3
1 2
3 1, 2, 3
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ADMINISTRATIVE CONTROLS 6.2.3 NUCLEAR SAFETY ASSURANCE GROUP NSAG FUNCTION 6.2.3. 1 The NSAG shall function to examine unit operating characteristics, NRC issuances, industry advisories, Licensee Event Reports, and other sources of unit design and operating experience information, including units of similar
- design, which may indicate areas for improving unit safety.
The NSAG shall make detailed recomnendations for revised procedures, equipment and modifications, maintenance activities, operations activities, or other means of improving unit safety to.the Director of Licensing and Assurance.
COMPOSITION 6.2.3.2 The NSAG shall be composed of at least five, dedicated, full-time engineers, with a minimum of three located on site.
Each shall have a bachelor s
degree in engineering or related science or qualifications meeting ANS.3.1 Draft Revision dated March 13, 1981, Section 4.2 or 4.4, or equivalent, as described in Section 4. 1 and at least 2 years professional level experience in his field, at least 1 year of which expel ience shall be in the nuclear field.
RESPONSIBILITIES 6.2.3.3 The NSAG shall be responsible for maintaining surveillance of unit activities to provide independent verification" that these activities are performed correctly and that human errors are reduced as much as practical.
RECORDS 6.2.3.4 Records of activities performed by the NSAG shall be prepared, main-
- tained, and forwarded each calendar month to the Director of Licensing and Assurance.
6.2.4 SHIFT TECHNICAL ADYISOR 6.2
~ 4.1 The Shift Technical Advisor shall provide advis'ory technical support to the Shift Manager in the areas of thermal hydraulics, reactor engineering, and plant analysis with regard to the safe operation of the unit.
The Shift Technical Advisor shall have a bachelor's degree or equivalent in a scientific or engineering discipline and shall have received specific training in the response and analysis of the unit for transients and accidents, and in unit design and layout, including the capabilities of instrumentation and controls in the control room.
- 6. 3 UNIT STAFF UALIFICATIONS 6.3.1 Each member of the unit staff shall meet or exceed the minimum qualifica-tions of ANSI/ANS N18.1-1971 for comparable positions, except for the Health Physics/
Chemistry Manager who shall meet or exceed the qualifications of Regulatory Guide 1.8, Revision 1-R, May 1977.
The licensed Operators and Senior Operators shall also meet or exceed the minimum qualifications of the supplemental requirements specified in Sections A and C of Enclosure 1 of the March 28, 1980 NRC letter to all licensees.
- Not responsible for sign-off function.
WASHINGTON NUCLEAR - UNIT 2 Amendment No.
18
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