Text

Amends 69 & 44 to Licenses DPR-70 & DPR-75,respectively, Revising Tech Specs Re Coolant Pump Operability Requirements While in Mode 3
	ML20141H309
Person / Time
Site:	Salem
Issue date:	12/30/1985
From:	Varga S; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20141H314	List: ML20141H309; ML20141H317;
References
	NUDOCS 8601130531
	Download: ML20141H309 (10)
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PUBLIC SERVICE ELECTRIC AND GAS COMPANY PHILADELPHIA ELEGIRIC COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELEGIRIC COMPANY DOCKET NO. 50-272 SALEM NUCLEAR GENERATING STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.69 License No. DPR-70 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 October 15, 1984, complies with the standards and requir-mets 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 (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 E.

The issuance of this amendment is in accordance with 10 CFR Part 31 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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y(2) Technical Specifications The Technical Specifica'tions contained in Appendices A and B, as revised through Amendment No.69 are hereby incorporated in the license. The licensee.shall

'. 9 operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of the date of its issuance.

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Attachment:

Changes to the Technical ',

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' ATTACHMENT TO LICENSE AMENDMENT NO. 69 FACILITY OPERATING LICENSE NO. DPR-70 DOCKET NO. 50-272 Revise Appendix A as follows:

Remove Pages Insert Pages 3/4 4-2 3/4 4-2 3/4 4-2a 3/4 4-2a 4

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l REACTOR COOLANT SYSTEM HOT STANDBY LIMITING CONDITION FOR OPERATION 3.4.1.2 a.

At least two of the reactor coolant loops listed below shall be OPERABLE:

1.

Reactor Coolant Loop 11 and its associated steam generator and reactor coolant pump, 2.

Reactor Coolant Loop 12 and its associated steam generator and reactor coolant pump, 3.

Reactor Coolant Loop 13 and its associated.

steam generator and reactor coolant pump, 4.

Reactor Coolant Loop 14 and its associated steam generator and reactor coolant punp.

b.

At least one of the above coolant loops shall be in operation

when the rod control systen is deenergized**.

c.

All of the above coolant loops shall be in operation when the rod control system is energized **.

APPLICABILITY:

MODE 3 ACTION:

a.

With less than the above required reactor coolant loops OPERABLE, restore the required loops to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , b.

Mth no reactor coolant loop in operation, suspend all operations involving a reduction in boron concentration of the Reactor Coolant System and immediately initiate corrective action to return the required coolant loop to operation.

SALEM - UNIT 1 3/4 4-2 Amendment No. 69

REACTOR COOLANT SYSTEM HOT STANDBY SURVEILLANCE REQUIREMENTS 4.4.1.2.1 At least the above required reactor ccolant pumps, if not in operation, shall be determined to be OPERABLE once per 7 days by verifying correct breaker alignments and. indicated power availability.

4.4.1.2.2 At least one cooling loop shall be verified to be in operation and circulating reactor coolant at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

4.4.1.2.3 The required steam generator (s) shall be determined OPERABLE by verifying secondary (side water level to be greater than or equal to 5% narrow range) at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

All reactor coolant purps rey be de-energized for up to I hour provided: (1) no operations are permitted that would cause dilution of the reactor coolant system boron concentration (2) core outlet temperature is maintained at least 10*F below saturation terperature, and (3) the rod control system is de -e ne rgi zed **

- The rod control system shall be considered de-energized when one or more of the following conditions exist:

1) Both Rod Drive MG set motor breakers are open.

2) Both Rod Drive MG set generator breakers are open.

3) A combination of at least three of the Reactor Trip and/or Reactor Trip Bypass Breakers are open.

If none of the aoove conditions for de-energizing the rod control system are met; the system shall be considered energized.

JALEh UNIT 1 3/4 4-2a Amendment No. 69

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PUBLIC SERVICE ELECTRIC AND GAS COMPANY PHILADELPHIA ELEGIRIC 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.44 License No. DPR-75 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 October 15, 1984 complies with the standards and require-ments 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 (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 l

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. 44, 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.

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Attachment:

Changes to the Technical Specifications Date of Issuance: December 30, 1985 e

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ATTACHMENT TO LICENSE AMENDMENT N0.44 FACILITY OPERATING LICENSE NO. DPR-75

. DOCKET NO. 50-311 Revise Appendix A as follows:

Remove Pages Insert Pages 3/4 4-2 3/4 4-2 3/4 4-2a 3/4 4-2a

REACTOR COOLANT SYSTEM HOT STANDBY LIMITING CONDITION FOR OPERATION 3.4.1.2 a.

At least two of the reactor coolant loops listed below shall be OPERABLE:

1.

Reactor Coolant Loop 21 and its associated steam generator and reactor coo.lant pump, 2.

Reactor Coolant Loop 22 and its associated steam generator and reactor coolant pump, 3.

Reactor Coolant Loop 23 and its associated steam generator and reactor coolant pump, 4

Reactor Coolant Loop 24 and its associated steam generator and reactor coolant pump.

b.

At least one of the above coolant loops shall be in operation

when the rod control ' system is deenergized**.

c.

All of the above coolant loops shall be in operation when the rod control system is energized **.

APPLICABILITY:

MODE 3 ACTION:

a.

With less than the above required reactor coolant loops OPERABLE, restore the required loops to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

b.

With no reactor coolant loop in operation, suspend all operations involving a reduction in boron concentration of the Reactor Coolant System and inmediately initiate corrective action to return the required coolant loop to operation.

SALEM - UNIT 2 3/4 4-2 Amendment No. 44

r REACTOR COOLANT SYSTEM HOT STANDBY SURVEILLANCE RESJIREMENTS 4.4.1.2.1 At least the above required reactor coolant pupps, if not in operation, shall be determined to be OPERABLE once per 7 days by verifying correct breaker alignments and indicated power availability.

4.4.1.2.2 At least one cooling loop shall be verified to be in operation and circulating reactor coolant at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

4.4.1.2.3 The required steam generator (s) shall be determined OPERABLE by verifying secondary side water level to be greater than or equal to 5% (narrow range) at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

All reactor coolant punps rey be de-energized for up to I hour provided: (1) no operations are permitted that would cause dilution of the reactor coolant system boron concentration (2) core outlet temperature is maintained at least 10*F below saturation temperature, and (3) the rod control system is de -energi zed **

l

- The rod control system shall be considered de-energized when one or more of the following conditions exist:

1) Both Rod Drive MG set notor breakers are open.

2) Both Rod Drive MG set generator breakers are open.

3) A combination of at least three of the Reactor Trip and/or Reactor Trip Bypass Breakers are open.

If none of the above conditions for de-energizing the rod control system are met; the system shall be considered energized.

SALEM - UNIT 2 3/4 4-2a Amendment to 44 l

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ML20141H309

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