ML20063C125
| ML20063C125 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 01/27/1994 |
| From: | Chris Miller Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20063C129 | List: |
| References | |
| NUDOCS 9402040058 | |
| Download: ML20063C125 (6) | |
Text
,
[pasc,k o
UNITED STATES
['(.et E
NUCLEAR REGULATORY COMMISSION
=j WASHINoTON, D.C. 20555-0001
- j EUBLIC SERVICE ELECTRIC & GAS COMPANY
' ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-354 HOPE CREEK GENERATING STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 64 License No. NPF-57 1.
The Nuclear Regulatory Comission (the Comission or the NRC) has found that:
A.
The application for amendment filed by the Public Servica Electric &
Gas Company (PSE&G) dated May 21, 1993, and supplemented on October 29, 1993, and November 16, 1993, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the-Act), and the Comission's rules and 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 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 set forth in 10 CFR Chapter I; 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 Spccifications as indicated in the attachment to this license amendment, l
and paragraph 2.C.(2) of Facility Operating License No. NPF-57 is hereby amended to read as follows:
(2) Technical Specifications and Environmental Protection plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 64, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated into the license.
PSE&G shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
9402040058 940127 PDR ADOCK 05000354 P
L
\\
, 3.
The license amendment is effective as of its date of issuance and shall be implemented within 60 days of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION-
&Au. h. @h Charles L. Miller, Director Project Directorate I-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: January 27, 1994 i
I i
i
ATTACHMENT TO LICENSE AMENDMENT NO. 64~
FACILITY OPERATING LICENSE NO. NPF-57 DOCKET NO. 50-354 Replace the following pages of the Appendix "A" Technical Specifications with the attached pages.
The revised pages are identified by Amcndment number and l
contain vertical lines indicating the areas of change.
Remove Insert 3/4 4-7 3/4 4-7 3/4 4-8 3/4 4-8 B 3/4 4-2a B 3/4 4-2a i
-l i
1 l
)
j i
REACTOR COOLANT SYSTEM 3/4.4.2 SAFETY / RELIEF VALVES SAFETY / RELIEF VALVES LINITING CONDITION FOR OPERATION i
3.4.2.1 The safety valve function of at least 13 of the following reactor coolant system safety / relief valves shall be OPERABLE *# with the specified code safety valve function lift settings:**
j 4
safety-relief valves 91108 psig 11%
5 safety-relief valves 9 1120 psig 11%
5 safety-relief valves 9 1130 psig 11%
APPLICABILITY:
OPERATIONAL CONDITIONS 1, 2 and 3.
ACTION:
a.
With the safety valve function of two or more of the above listed fourteen safety / relief valves inoperable, be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
l b.
With one or more safety / relief valves stuck open, provided that
)
suppression pool average water temperature is less than 110*F, close the stuck open safety relief valve (s); if unable to close the stuck open valve (s) within 2 minutes or if suppression pool average water temperature is 110*F or greater, place the reactor mode switch in the Shutdown position.
c.
With one or more of the above required safety / relief valve acoustic moni-tors inoperable, restore the inoperable monitors to OPERABLE status within 7 days or 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 in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
- SRVs which perform as ADS function must also satisfy the OPERABILITY requirements of Specification 3.5.1, ECCS-Operating.
- The lift setting pressure shall correspond to ambient conditions of the valves at nominal operating temperatures and pressures.
- SRVs which perform a low-low set function must also satisfy the OPERABILITY requirements of Specification 3.4.2.2, Safety / Relief Valves Low-Low Set Function.
HOPE CREEK 3/4 4-7 Amendment No. 64
REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS 4.4.2.1 The acoustic monitor for each safety / relief valve shall be demonstrated OPERABLE with the setpoint verified to be s 30% of full open noise level ** by performance of a:
a.
CHANNEL FUNCTIONAL TEST at least once per 31 days, and a b.
CHANNEL CALIBRATION at least once per 18 months *.
4.4.2.2 At least 1/2 of the safety relief valve pilot stage assemblies shall be removed, set pressure tested and reinstalled or replaced with spares that have been previously set pressure tested and stored in accordance with manufacturer's recommendations at least once per 18 months, and they shall be rotated such that all 14 safety relief valve pilot stage assemblies are removed, set pressure tested and reinstalled or replaced with spares that have been previously set pressure tested and stored in accordance with manufacturer's recomendations at least once per 40 months.
4.4.2.3 The safety relief valve main (mechanical) stage assemblies shall be set pressure tested, reinstalled or replaced with spares that have been previously set pressure tested and stored in accordance with manufacturer's recomendations at least once every 5 years.
- The provisions of Specification 4.0.4 are not applicable provided the Surveillance is performed within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after reactor steam pressure is adequate to perform the test.
- Initial setting shall be in accordance with the manufacturer's recomendations. Adjustment to the valve full open noise level shall be accomplished after the initial noise traces have been analyzed.
HOPE CREEK 3/4 4-8 Amendment No. 64
c BASES i
valves is required ~to limit reactor-pressure to within ASME III allowable' values for the worst. case transient.
Demonstration of the safety relief valve. lift settings. occurs only during shutdown.
The safety relief valve pilot stage assemblies are set pressure tested in accordance with the recommendations of General Electric SIL No.196, Supplement 14 (April 23, 1984), " Target Rock 2-Stage SRV Set-Point Drift." Set pressure tests of the safety relief valve main-(mechanical) stage are conducted i
at least once every 5 years.
1 The low-low set system ensures that safety / relief valve discharges are minimized for a second opening of these valves, following any overpressure transient. This is achieved by automatically lowering ~ the closing setpoint of two valves and lowering the opening setpoint of two valves following the-initial opening.
In tnis way, the frequency and magnitude of the containment blowdown duty cycle is substantially reduced. Sufficient redundancy is provided for the low-low set system such that failure of any one valve to open t
or close at its reduced setpoint does not violate the design basis.
l e
i L
1
)
i 9
HOPE CREEK-B 3/4 4-2a Amendment No. 64 -
- i