ML20100A236

Amends 60 & 31 to Licenses DPR-70 & DPR-75,respectively, Modifying Unit 1 Tech Specs,Table 3.3-1 (Action 1) & Table 3.3-3 (Action 13) to Read Same as Unit 2 Tech Spec Tables

ML20100A236
Person / Time
Site:	Salem
Issue date:	03/08/1985
From:	Varga S Office of Nuclear Reactor Regulation
To:
Shared Package
ML20100A239	List: ML20100A236 ML20100A243
References
NUDOCS 8503250399
Download: ML20100A236 (13)

Text

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UNITED STATES E

NUCLEAR REGULATORY COMMISSION o

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W74HINGTON, D. C. 20555

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PUBLIC SERVICE ELECTRIC AND GAS COMPANY PHILADELPHIA ELECTRIC COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELEGIRIC COMPANY DOCKET N0. 50-272 SALEM NUCLEAR GENERATING STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.60

^~ n License No. DPR-70 j-1.

The Nuclear Regulatory Comission (the Comission) has found that:

A.

The application for amendment by Public Service Electric and Gas Company, Philadelphia Electric Company, Delmarva Power and Light Company and Atlantic City Electric Company (the licensees) dated December 27, 1983 and supplemented February 25, 1985, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's e

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 (1) 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 i

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 Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-70 is hereby amended to read as follows:

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(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 60, 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 the date of its issuance.

FOR THE NUCLEAR REGULATORY COMMISSION L

ah a ef te Operating Reacto Branch #1 Division of Licensing

Attachment:

J Changes to the Technical Specifications Date of Issuance: March 8, 1985 r!

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ATTACHMENT TO LICENSE AMENDMENT N0. 60 FACILITY OPERATING LICENSE N0. DPR-70 DOCKET NO. 50-272 Revise Appendix A as follows:

Remove Pages Insert Pages 3/4 3-5 3/4 3-5 3/4 3-9 3/4 3-9 3/4 3-21 3/4 3-21 I.

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1

_ TABLE 3.3-1 (Continued)

TABLE NOTATION With the reactor trip system breakers in the closed position and the control rod drive system capable of rod withdrawal.

"The channel (s) associated with the protective functions derived from the out of service Reactor Coolant Loop shall be placed in the tripped condition.

1. The provisions of Specification 3.0.4 are not applicable.

1. 1. High voltage to detector may be de-energized above P-6.

ACTION STATEMENTS ACTION 1 With the number of channels OPERA 8LE one less than required by J

the Minimus Channels OPERABLE requirement, be in HOT STANOBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />; however, one channel may be bypassed for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing per Specification 4.3.1.1 l

provided the other channel is OPERABLE.

ACTION 2 - With the numaer of OPERA 8LE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the following conditions are satisfied:

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a.

The inoperable channel is placed in the tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

b.

The Minimum Channels OPERABLE requirement is met; however, one additional channel may be bypassed for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing per Specification 4.3.1.1.

c.

Either, THERNAL POWER is restricted to < 75t of RATED THERMAL and the Power Range, Neutron Flux trip.

setdoint is reduced to < 85% of RATED THERMAL POWER within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />; or, the QUADRANT POWER TILT RATIO is monitored at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

ACTION 3 - With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement and with the THERMAL POWER level:

I SALEM - UNIT 1 3/4 3-5 Amendment No. 60

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TABLE 3.3-2 vs REACTOR TRIP SYSTEM INSTRUMENTATION RESPONSE TIMES e

g FUNCTIONAL UNIT RESPONSE TIME 1.

Manual Reactor. Trip NOT APPLICABLE f

2.

Power Range, Neutron Flux 1 0.5 seconds

• 3.

Power Range, Neutron Flux, j

High Positive Rate NOT APPLICABLE 4.

Power Range, Neutron Flux, 3

High Negative Rate 1 0.5 seconds

• g 5.

Intermediate Range, Neutron Flux NOT APPLIrsRLE 3

6.

Source Range, Neutron Flux NOT APPLICABLE

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7.

Overtemperature AT 5 4 0 seconds

• I 8.

Overpower AT NOT APPLICABLE 9.

Pressurizer Pressure--Low 1 2.0 seconds 5

10.

Pressurizer Pressure--High 1 2.0 seconds b

11. Pressurizer Water Level--High NOT APPLICABLE S

• Neutron detectors are exempt from response time testing. Response tinie of the neutron flux signal portion of the channel shall be measured from detector output or input of first electronic component in channel,.

a

TABLE 3.3-2 (Continued)

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- REACTOR TRIP SYSTEM INSTRUMENTATION RESPONSE TIMES Eq FUNCTIONAL UNIT RESPONSE TIME

12. Loss of Flow - Single Loop (Above P-8) 1 1.0 seconds

13. Loss of Flow - Two Loops (Above P-7 and below P-8) 1 1.0 seconds

14. Steam Generator Water Level--Low-Low 1 2.0 seconds

15. Steam /Feedwater Flow Mismatch and m2 Low Steam Generator Water Level NOT APPLICABLE

16. Undervoltage-Reactor Coolant Pumps 1 1.2 seconds

17. Underfrequency-Reactor Coolant Pumps 1 0.6 seconds

18. Turbine Trip A.

Low Fluid Oil Pressure NOT APPLICABLE B.

Turbine Stop Valve NOT APPLICABLE 19.

Safety Injection Input from ESF NOT APPLICABLE 20.

Reactor Coolant Pump Breaker Position Trip NOT APPLICABLE

TABLE.1.3-3 (Continued)

TAllLE NOTATION

1. rip function may be bypassed in this MODE below P-11.

T

1. 1. rip function may be bypassed in this MODE below P-12.

T The channel (s) associated with the protective functions derived from the out of service Reactor Coolant Loop shall be placed in the tripped mode.

The provisions 'of Specification 3.0.4 are not appitcable.

ACTION STATD8ENTS ACTION 13 - With the number of OPERA 8LE Channels one less than the T Number of Channels, be in HOT STAND 8Y within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />; however, one channel may be bypassed for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance l

testing per Specification 4.3.2.1.1.

ACTION 14 - With the ntsaber of OPERA 8LE Channels one less than the To Number of Channels, operation may proceed until performance of the next required CHANNEL FUNCTIONAL TEST, provided the inoperable channel is placed in the tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

ACTION 15 - With a channel associated with an operating loop inoperable, restore the inoperable channel to OPERA 8LE status within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or be in HOT SHUTDOWN within the following 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />; however, one channel associated with an operating loop may be bypassed for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing per Specification 4.3.2.1.1.

ACTION 16 - With the number of OPERABLE Channels one less than the Total Number of Channels, operation may proceed provided the inoperable channel is placed in the bypassed condition and the Minimum Channels OPERA 8LE requirement is demonstrated within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />; one additional channel may be bypassed for up I

.I to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing per Specification 4.3.2.1.1.

l SALEM - UNIT 1 3/4 3-21 Amendment No. 60 f

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UNITED STATES 8

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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.31 License No. DPR-75 1.

The Nuclear Regulatory Comission (the Comission) has found that:

L A.

The application for amendment by Public Service Electric and Gas Company, Philadelphia Electric Company, Delmarva Power and Light Company and Atlantic City Electric Company (the licensees) dated December 27, 1983 and supplemented February 25, 1985, 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; i

B.

The facility will operate in confonnity 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 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.31, 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 the date of its issuance.

F0 THE NUCLEAR REGULATORY COMMISSION 1

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arga, en Operating Reactors B

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Division of Licensing

Attachment:

~ Changes to the Technical Specifications Date of Issuance:

March 8, 1985 l

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ATTACHMENT TO LICENSE AMENDMENT N0. 31 FACILITY OPERATING LICENSE NO. DPR-75 DOCKET N0. 50-311 Revise Appendix A as follows:

Remove Pages Insert Pages 3/4 3-9 3/4 3-9 3/4 8-4 3/4 8-4

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y TABLE 3.3-2 r-REACTOR TRIP SYSTEN INSTRtMENTATION RESPONSE TIES E

g FUNCTIONAL tmIT RESPONSE TINE

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1.

Manual Reactor Trip NOT APPLICABLE 2.

Power Range, Neutron Flux 5 0.5 seconds

• 3.

Power Range, Neutron Flux, High Positive Rate NOT APPLICABLE 4.

Power Range, Neutron Flux, g

High Negative Rate 5 0.5 seconds" y

5.

Intermediate Range, Neutron Flux NOT APPLICA8LE 6.

Source Range, Neutron Flux NOT APPLICA8LE 7.

Overtemperat:;re AT 54 0 seconds

• 8.

Overpower AT NOT APPLICA8LE 9.

Fressarszer Pressure--Low

$ 2.0 seconds

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10.

Pressurizer Pressure--High 5 2.0 seconds s*g

11. Pressurizer water Level--High NOT APPLICABLE 5

S

• Neutron detectors are exempt from response time testing.

Response time of the neutron flux signal portion of the channel shall be measured from detector output or input of first electronic component in channel.

TABLE 3.3-2 (Continued) 9 REACTOR TRIP SYSTEM INSTRUE NTATION RESPONSE TIMES FUNCTIONAL UNIT RESPONSE TIME

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12.

Loss of Flow - Single Loop (Above P-8) 5 1.0 seconds 13.

Loss of Flow - Two Loops (Above P-7 and below P-8) 5 1.0 seconds 14.

Steam Generator Water Level--Low-Low 5 2.0 seconds w

15. Steam /Feedwater Flow Mismatch and Low Steam Generator Water Level NOT APPLICABLE w

h

16. Undervoltage-Reactor Coolant Pumps 5 1.2 seconds

17. Underfrequency-Reactor Coolant Pumps 5 0.6 seconds 18.

Turbine Trip A.

Low Fluid Oil Pressure NOT APPLICA8LE 8.

Turbine Stop Valve NOT APPLICABLE 19.

Safety Injection Input from ESF NOT APPLICABLE 20.

Reactor Coolant Pump Breaker Position Trip NOT APPLICA8LE

21. Reactor Trip Breakers NOT APPLICABLE 22.

Automatic Trip Logic NOT APPLICABLE

ELECTRICAL POWER SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) 5.

Verifying that on a simulated loss of the diesel generator (with offsite power not available), the diesel generator cannot be auto-connected to a 7oaded bus and that subsequent loading of the diesel generator is in accordance with design requirements.

6.

Simulating a loss of offsite power in conjunction with an ESF actuation test signai, and a)

Verifying de-energization of the vital busses and load shedding from the vital busses.

b)

Verifying the diesel starts from ambient condition on the auto-start signal, energizes the vital busses with perma-nently connected loads within 13 seconds, energizes the auto-connected emergency (accident) loads through the load sequencer and operates for greater than or equal to 5 minutes while its generator is loaded with the emergency loads.

The steady state voltage and frequency of the emergency busses shall be maintained at 4160 t 420 volts and 60 t 1.2 Hz during this test.

c)

Verifying that all automatic diesel generator trips, except engine overspeed, lube oil pressure low, 4 KV Bus differential and generator differential, are automatically bypassed upon loss of voltage on the vital bus concurrent with a safety injection actuation signal.

7.

Verifying the diesel generator operates for at least 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

During the first 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> of this test, the diesel generator shall be loaded to greater than or equal to 2860 Kw and during the remaining 22 hours2.546296e-4 days <br />0.00611 hours <br />3.637566e-5 weeks <br />8.371e-6 months <br /> of this test, the diesel generator shall be loaded to greater than or equal to 2600 kw. Within 5 minutes after completing this 24-hour test, perform Specification 4.8.1.1.2.c.4.

The steady state voltage and frequency shall be l

maintained at 4160 t 420 volts and 60 1 1.2 Hz during this test.

8.

Verifying that the auto-connected loads to each diesel generator do not exceed the 2000-hour rating of 2760 kw.

9.

Verifying that with the diesel generator operating in a test mode (connected to its bus), a simulated safety injection signal overrides the test mode by (1) returning the diesel generator to standby operation and (2) automatically energizes the emergency loads with offsite power.

SALEM - UNIT 2 3/4 8-4 Amendrent No. 31