ML20072V592

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Amends 156 & 137 to Licenses DPR-70 & DPR-75,respectively, Eliminating Required Loss of Offsite Power Plus an Engineering Safety Feature Actuation Signal Test Following 24 H Endurance Test
ML20072V592
Person / Time
Site: Salem  PSEG icon.png
Issue date: 09/08/1994
From: Thadani M
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20073A000 List:
References
NUDOCS 9409200062
Download: ML20072V592 (10)


Text

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om 44 UNITED STATES o

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NUCLEAR REGULATORY COMMISSION f

WASHINGTON D.C. 20665 0001

.....,o PUBLIC SERVICE ELECTRIC & GAS COMPANY PHILADELPHIA ELECTRIC COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-272 SALEM NVCLEAR GENERATING STATION. UNIT N0. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 156 License No. DPR-70 1.

The Nuclear Regulatory Commission (the Commission or the NRC) has found that:

A.

The application for amendment filed by the Public Service Electric &

Gas Company, Philadelphia Electric Company, Delmarva Power and Light Company and Atlantic City Electric Company (the licensees) dated April 12, 1994 and supplement dated July 15, 1994, 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 application, the provisions of the Act, and the rules and regulations of the Commission; 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 set forth in 10 CFR Chapter I; 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.

2.

Accordingly, the license is amended by changes to the Technical Specifica-tions 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:

9409200062 940908 PDR ADOCK 05000272 P

PDR

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(2) Technical Specifications and Environmental' Protection Plan i

The Technical. Specifications contained in Appendices-A and B, as' revised through Amendment No. 156, are hereby incorporated in the i

license. The licensee shall operate the. facility in accordance with the Technical Specifications.

j 3.

This license amendment is effective.as of its date of issuance and shall be implemented within 90 days of the date of issuance.

g FOR THE NUCLEAR REGULATORY COMMISSION

/

b' C (h

Mohan C. Thadani, Acting Director Project Directorate I-2 j

Division of Reactor Projects - I/II

-i Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: September 8, 1994 i

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ATTACHMENT TO LICENSE AMENDMENT NO.156 FACILITY OPERATING LICENSE NO. DPR-70 DOCKET NO.'50-272 Revise Appendix A as follows:

Remove Paaes insert Paaes 3/4 8-5 3/4 8-5 f

3/4 8-Sa 3/4 8-5a 1

f 5

ELECTRICAL POWER SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) c)

Verifying that all nonessential automatic diesel generator trips (i.e., other than 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 2760-2860 kw.**

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 2500-2600 kw**.

The steady state voltage and frequency shall be maintained at = 3950 and 4580 volts and 60 1 1.2 Hz during this test.

s 8.

Verifying that the auto-connected loads to each diesel generator do not exceed the two hour rating of 2860 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 energizing the emergency loads with offsite power, At least once per ten years or after any modifications which could affect e.

diesel generator interdependence by starting all diesel generators simultaneously *, during shutdown, and verifying that all diesel generators accelerate to at least 900 rpm in less than or equal to 10 seconds, j

e f.

At least once per 18 months: the following test shall be performed within 5 minutes of diesel shutdown after the diesel has operated for at least two hours at 2500-2600 kw**?

Verifying the diesel starts and accelerates to 900 rpm in less than or equal to 10 seconds *, The generator voltage and frequency shall be I

3950 volts and s 4580 volts and 60 1.2 Hz within 13 seconds after the

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start signal.

4.8.1.1.3 The diesel fuel oil storage and transfer system shall be

.I demonstrated OPERABLE:

~'

a.

At least once per 31 days by:

1.

Verifying the level in each of the above required 20,000 gallon fuel storage tanks.

2.

Verifying that both fuel transfer pumps can be started and transfer fuel from the 20,000 gallon storage tanks to the day tanks.

SALEM - UNIT 1 3/4 8-5 Amendment No.156

o ELECTRICAL POWER SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) b.

At least once per 92 days by verifying that a sample of diesel fuel from each of the above required 20,000 gallon fuel storage tanks is'within the acceptable limits specified in Table 1 of ASTM D975-77 when checked for viscosity, water and sediment.

4.8.1.1.4 Reoorts - All diesel generator failures, valid or non-valid,'shall

~

be reported to the Commission in a Special Report pursuant to Specification 6.9.2 within 30 days.

Reports of diesel generator failures shall include the information recommended in Regulatory Position C.3.b of Regulatory Guide 1.108, Revision 1, August 1977.

If the number of failures in the last 100 valid tests (on a per nuclear unit basis) is greater than or equal to 7, the report shall be supplemented to include the additional information recommended in Regulatory Position C.3.b of Regulatory Guide 1.108, Revision 1, August 1977.

F Surveillance testing shall be conducted in accordance with the manufacturer's recommendations regarding engine'prelube, warm-up and' loading (unless loading times are specified in the individual Surveillance Requirements).

    • - This band is meant as guidance to preclude routine exceedances of the diesel generator manufacturer's design ratings. Loads in excess of this band for special testing or momentary variations due to changing bus loads shall not invalidate the test.

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SALEM - UNIT 1 3/4 d-5a Amendment No.156 1

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y-UNITED STATES j

NUCLEAR REGULATORY COMMISSION WASHINGTON D.C. 20665 0001

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PUBLIC SERVICE ELECTRIC & GAS COMPANY PHILADELPHIA ELECTRIC COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-311 SALEM NUCLEAR GENERATING STATION. UNIT N0. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 137 License No. DPR-75 1.

The Nuclear Regulatory Commission (the Commission or the NRC) has found that:

i A.

The application for amendment filed by the Public Service Electric &

Gas Company, Philadelphia Electric Company, Delmarva Power and Light Company and Atlantic City Electric Company (the licensees) dated April 12, 1994 and supplement dated July 15, 1994, 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 application, the provisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance: (i) that the activities authorized by I

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 set forth in 10 CFR Chapter I;

)

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.

2.

Accordingly, the license is amended by changes to the Technical Specifica-tions as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-75 is hereby l-amended to read as follows:

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' (2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in AppendicesL A and B, as revised through Amendment No.137.. 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 its' date of issuance and shall' be implemented before restart from the eighth refueling outage,: currently scheduled to begin on October 15, 1994.

FOR THE NUCLEAR REGULATORY 2 COMMISSION

&istau CRik Mohan C.:Thadani, Acting Director Project Directorate I-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation Att'achment:

Changes to the Technical Specifications

.i Date of Issuance:

September 8, 1994 t

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ATTACHMENT TO LICENSE AMENDMENT NO. 137 FACILITY OPERATING LICENSE N0. DPR-75 i

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

Remove Paaes Insert Paaes 3/4 8-5 3/4 8-5 3/4 8-6 3/4 8-6 l

1 i

1

ELECTRICAL POWER SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) c)

Verifying that all nonessential automatic diesel generator trips (i.e., other than 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 2760-2860 kw**.

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 2500-2600 kw**.

The steady state voltage and frequency shall be maintained at 2 3950 and s 4580 volts and 60 1.2 Hz during this test 8.

Verifying that.the auto-connected loads to each diesel generator do not exceed the two hour rating of 2860 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 energizing the emergency loads with offsite power.

e.

At least once per 10 years or after any modifications which could affect diesel generator interdependence by starting all diesel generators simultaneously *, during shutdown, and verifying that all diesel generators accelerate to at least 900 rpm in less than or equal to 10 seconds.

f.

At least once per 18 months, the following test shall be performed within 5 minutes of diesel shutdown after the diesel has operated for at least two hours at 2500-2600 kw":

Verifying the diesel starts and accelerates to 900 rpm in less than or equal to 10 seconds *.

The generator voltage and frequency shall be a 3950 volts and s 4580 volts and 60 1 1.2 Hz within 13 seconds after the start signal.

4.8.1.1.3 The diesel fuel oil storage and transfer system shall be demonstrated OPERABLE:

a.

At least once per 31 days by:

1.

Verifying the level in each of the above required 20,000 gallon fuel storage tanks.

2.

Verifying that both fuel transfer pumps can be started and transfer fuel from the 20,000 gallon storage tanks to the day tanks.

SALEM - UNIT 2 3/4 8-5 Amendment No. 137

t r

ELECTRICAL POWER SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) b.

At least once per 92 days by verifying that a sample of diesel fuel from each of the above required 20,000 gallon fuel storage tanks is within the acceptable limits specified in Table 1 of ASTM D975-77 when checked for viscosity, water and sediment.

4.8.1.1.4 Recorts - All diesel generator failures, valid or non-valid, shall be reported to the Commission in a Special Report pursuant to Specification 6.9.2 within 30 days.

Reports of diesel generator failures shall include the information recommended in Regulatory Position C.3.b.of Regulatory Guide 1.108, Revision 1, August 1977.

If the number of failures in the last 100 valid tests (on a per nuclear unit basis) is greater than or equal to 7, the report shall be supplemented to include the additional information recommended in Regulatory Position C.3.b of Regulatory Guide 1.108, Revision 1, August 1977 l

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l Surveillance testing shall be conducted in accordance with the manufacturer's recommendations regarding engine prelube, warm-up and loading (unless loading times are specified in the individual Surveillance Requirements).

This band is meant as guidance to preclude routine exceedances of the diesel generator manufacturer's design ratings. Loads in excess of this band for special testing or momentary variations due to changing bus loads shall not invalidate the test.

SALEM - UNIT 2 3/4 8-6 Amendment No.137