ML20078Q328
| ML20078Q328 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 02/02/1995 |
| From: | Butler W Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20078Q329 | List: |
| References | |
| NUDOCS 9502210208 | |
| Download: ML20078Q328 (5) | |
Text
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4 UNITED STATES
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j NUCLEAR REGULATORY COMMISSION o
R WASHINGTON, D.C. 200eH1001
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BOSTON EDISON COMPANY DOCKET NO. 50-293 PILGRIM NUCLEAR POWER STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 157 License No. DPR-35 1.
The Nuclear Regulatory Comission (the Comission or the NRC) has found that:
A.
The application for amendment filed by the Boston Edison Company (the licensee) dated September 6, 1994, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),
and the Comission's rules and regulations; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations'of the Comission; 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 Comission's regulations; D.
The issuance of this amendment will not be inimical to the comon 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 Comission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifica-tions as indicated in the attachment to this license amendment.
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9502210208 950202 PDR ADOCK 05000293 P
3.
This license amendment is effective as of its date of issuance and shall be implemented within 30 days.
t FOR THE NUCLEAR REGULATORY COMMISSION Walter R. Butler, Director Project Directorate I-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
February 2. 1995
O ATTACHMENT TO LICENSE AMENDMENT NO.157 FACILITY OPERATING LICENSE NO. DPR-35 DOCKET NO. 50-293 Replace the following pages of the Appendix A Technical Specifications with the attached pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.
Ramsyg Insert 3/4. 5-9 3/4.5-9 B3/4.5-6 B3/4.5-6 t
i LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT 3,5 CORE AND CONTAINMENT COOLING 4.5 CORE AND CONTAINMENT COOLING SYSTEMS (Cont)
SYSTEMS (Cont)
H.
Maintenance of Filled Discharte Eing (Cont)
- 2. Following any period where the LPCI system or core spray systems have not been required to be operable, the discharge piping of the inoperable system shall be vented from the high j
point prior to the return of the system to service.
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- 3. Whenever the HPCI or RCIC system is lined up to take suction from the torus, the discharge piping of the HPCI and RCIC shall be vented from the high point of the system and water flow observed on a monthly basis.
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39 -135, 157 3/4.5-9 Amendment No.
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BASES:
3.5 CORE AND CONTAINMENT COOLING SYSTEMS (Cont) occur. A potential draining of the reactor vessel (via control rod blade
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leakage) would allow this water to enter into the torus and after approximately 140,000 gallons have accumulated (needed to meet minimum NPSH requirements for the LPCI and/or core spray pumps), the torus would be able to nerve as a common suction header. This would allow a closed loop operation of the LPCI system and the core spray system (once re-aligned) to the torus.
In addition, the other core spray system is lined up to the condensate s torage tanks which can supplement the refuel cavity and dryer / separator poo'. water to provide core flooding, if required.
Specification 3.9 must also be consulted to determine o.ther requirements for the diesel generators.
G.
Deleted H.
Maintenance of Filled Discharge Pipe If the discharge piping of the core spray, LPCI system, HPCI, and ALIC are not filled, a water hammer can develop in this piping when the pump and/or pumps are started. An analysis has been done which shows that if a water hammer were to occur at the time at which the system were required, the system would still perform its design function. However, to minimize damage to the discharge piping and to ensure added margin in the operation of these systems, this Technical Specification requires the discharge lines to be filled whenever the system is in an operable condition.
An acceptable method of ensuring that the lines are full is to vent at the high points.
The monthly frequency is based on the gradual nature of void buildup in the ECCS piping, the procedural controls, and operating experience.
4.5 CORE AND CONTAINMENT COOLING SYSTEMS SURVEILIANCE FREOUENCIES The testing interval for the core and containment cooling systems is based on industry practice, quantitative reliability analysis, judgment and practicality. The core cooling systems have not been designed to be fully testable during operation.
For example, in the case of the HPCI, automatic initiation during power operation would result in pumping cold water into the reactor vessel which is not desirable.
Complete ADS testing during power operation couses an undesirable loss-of-coolant inventory. To increase the availability of the core and containment cooling systems, the components which make up the system; i.e.,
instrumentation, pumps, valves, etc., are tested frequently.
The pumps and motor operated valves are tested in accordance with ASME B&PV Code,Section XI (IWP and IWV, except where specific relief is granted) to assure their operability.
The frequency and methods of testing are described in the PNPS IST program. The PNPS IST l'rogram is used to assess the operational readiness of pumps and valves that are safety-related or important to safety. When components are tasted and found inoperable the impact on system operability is determined, and corrective action or Limiting Conditions of Operation are initiated. A sinulated automatic actuation test once each cycle combined with code inservice testing of the pumps and valves is deemed to be adequate testing of these systems, l
The surveillance requirements provide adequate assurance that the core and containment cooling systems will be operable when required.
39 -135,-149, 157 B3/4.5-6 Amendment No.
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