ML18086B148
| ML18086B148 | |
| Person / Time | |
|---|---|
| Site: | Salem |
| Issue date: | 12/15/1981 |
| From: | Varga S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML18086B149 | List: |
| References | |
| NUDOCS 8112290043 | |
| Download: ML18086B148 (6) | |
Text
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 PUBLIC SERVICE ELECTRIC AND GAS COMPANY PHILADELPHIA ELECTRIC COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-311 SALEM NUCLEAR GENERATING STATION, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 3 License No. DPR-75
- 1.
The Nuclear Regulatory Corrmission (the Cormnission) has found that:
A.
The request for amendment by Public Service Electric and Gas Company, Philadelphia Electric Company, and Delmarva Power and Light Company and Atlantic City Electric Company, (the 1 i cen sees) dated November 9, 1981 (as confirmed by letter dated November 18, 1981), complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the applicdtion, the provisions of the Act, and the rules and regulations of
- the Cammi ss ion; 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; 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.
8112290043 811215
~DR ADOCK 05000311 PDR
- 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-75 is hereby amended to read as follows:
(2)
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 3, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
- 3.
This license amendment is effective as of November 9, 1981.
Attachment:
Changes to the Technical Specifications Date of Issuance:
December 15, 1981 fO;R THE NUqE~EGULATORY
- \\1 d 1 J COMMISSION
~"A~ Lk~)~~,{r Ooerating Reactors; anch #1 Division of Licens1 g
ATTACHMENT TO LICENSE AMENDMENT NO. 3 FACILITY OPERATING LICENSE NO. DPR-75 DOCKET NO. 50-311 Revise Appendix A as follows:
Remove Pages 3/4. 5-3 3/ 4 5-6 Insert Pages 3/4 5-3 3/4 5-6 3/4 5-6a
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- t EMERGENCY CORE COOLING SYSTEMS ECCS SUBSYSTEMS - Tavg ~ 350°F LIMITING CONDITION FOR OPERATION 3.5.2 Two independent ECCS subsystems shall be OPERABLE with each subsystem co_mpri sed of:
- a.
-One OPERABLE centrifugal charging pump,
- b.
One OPERABLE safety injection pump,
- c.
One OPERABLE residual heat removal heat exchanger,
- d.
One OPERABLE residual heat removal pump, and
- e.
An OPERABLE flow path capable of taking suction from the refueling water storage tank on a safety injection signal and t~ansferring suction to the containment sump during the recirculation phase of operation.
APPLICABILITY:
MODES 1, 2 and 3.
ACTION:
- a.
With one ECCS subsystem inoperable, restore the inoperable subsystem to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in 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 />.*
- b.
In the event the ECCS is actuated and injects water into the Reactor Coolant System, a Special Report shall be prepared and submitted to the Commission pursuant to Specification 6.9.2 within 90 days describing the circumstances of the actuation and the total accumulated actuation cycles to date.
The current value of the usage factor for each affected safety injection nozzle shall be provided in this Special Report whenever its value exceeds 0.70.
The tine for completion of repairs to the No. 22 centrifugal charging pump shall be extended from 0527 hours0.0061 days <br />0.146 hours <br />8.713624e-4 weeks <br />2.005235e-4 months <br /> on November 10, 1981 to 0527 hours0.0061 days <br />0.146 hours <br />8.713624e-4 weeks <br />2.005235e-4 months <br /> on Noveni>er 12, 1981. If repairs are not completed by that time, the unit shall be placed in HOT SHUTOOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
SALEM - UNIT 2 3/4 5-3 Amendment No. 3 I
--*-e.,
EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)
- f.
By verifying that each of the following pumps develops the indicated*
discharge pressure on recirculation flow whe~ tested pursuant to Specification 4.0.5:
- 1.
Centrifugal charging pump
~ 2400 psig
~ 1425 psig
~ 165 psig
- 2.
Safety Injection pump
- 3.
- g.
By verifying the correct position of each of the following ECCS throttle valves:
- 1.
Within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> following completion of each valve stroking operation or maintenance on the valve when the ECCS subsystems are required to be OPERABLE.
- 2.
At least once per 18 months.
HPSI System Valve Number 21 SJ 16 22 SJ 16 23 SJ 16 24 SJ 16 LPSI System Valve Number 21 SJ 138 22 SJ 138 23 SJ 138 24 SJ 138 21 SJ 143 22 SJ 143 23 SJ 143 24 SJ 143
- h.
By performing a flow balance test, during shutdown, following completion of modifications to the ECCS subsystems that alter the subsystem flow characteristics and verifying that:*
- l.
For safety injection lines, with a.single pump running:
a)
The sum of the injection line flow rates, excluding the line with the highest flow rate, is ~ 463 gpm, and b)
The total pump flow rate is ~ 650 gpm.
- 2.
For centrifugal charging pump lines, with a single pump running:
SALEM - UNIT 2 a)
The sum of the injection line flow rates, excluding the line with the highest flow rate, is > 346 gpm, and b)
The total pump flow rate is < 550 gpm.
3/4 5-6 Amendment No. 3 I
EMERGENCY CORE COQLING SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)
- (footnote from page 3/ 4 5-6)
After co~pletion of repairs to the No. 22 centrifugal charging pump on or about Uovember 12, 1981, the pump shall be tested pursuant to specification 4.0.5 and system perfonnance calculations be perfonred to verify that the pump characteristics are not significantly different.
Flow balance testing pursuant to specification 4.5.2.h shall be perfonned the next tine the unit is in COLD SHUTDOHN.
SALEM UNIT 2 3/4 5-6a Amendment No. 3 *