Text

Amend 5 to License NPF-13,changing Schedule for Completion of Corrective Actions for safety-related Electrical Equipment to End of First Refueling Outage
	ML20070K471
Person / Time
Site:	Grand Gulf
Issue date:	12/20/1982
From:	Eisenhut D; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20070K473	List: ML20070K471; ML20070K484; ML20070K515;
References
	NUDOCS 8212300188
	Download: ML20070K471 (7)
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MISSISSIPPI POWER AND LIGliT COMPAllY tilDDLE SOUTH ENERGY, INC.

SOUTH MISSISSIPPI ELECTRIC POWER ASSOCIATION DOCKET NO. 50-416 l

GRAND GULF NUCLEAR STATION, UNIT 1 ANIEHOMENT TO FACILITY OPERATING LICENSE License No. HPF-13 Amendment No. 5 1.

The Nuclear Regulatory Comission (the Comission or the NRC) has found i

that:

A.

The two applications for the amendments filed by the Mississippi Power and Light Company dated September 13, 1982 comply with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's 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 regulations of the Commission; 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 conoliance with the Commission's regulations; j

D.

The issuance of this amendment will not be inimical to the conmon 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 as follows:

A.

Page changes to the Technical Soccifications as indicated in the attachment to this license anendment and paragraph 2.C.(2) to read as follows:

(2) The Technical Specifications contained in Appendix A, as revised through Amendnent No. 5, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license.

The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

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. B.

Change paragraph 2.C.12.c to read as follows:

2.C.12 Environmental Qualifications (c) MP&L shall complete the following actions on schedules specified with each:

(1) Prior to exceeding 5% thermal power, MP&L shall implement the aging requirements specified in Section 3.7 and Section 4.3 of Appendix H of Supplement Ho. 2 of the Safety Evaluation Report.

(ii) Corrective actions for equipment identified in Exhibit B (Equipment Requiring Additional Information and/or Corrective Action) of Appendix H to Supplement No. 2 of the Safety Evaluation Repcrt shall be completed by the end of the first refueling outage.

(iii) For equipment identified by MP&L in letters dated September 1, 1981, December 21, 1981, and April 8, 1982, requiring either replacement or modification to justify interim operation, MPAL shall complete this work prior to exceeding 5% thermal power.

3.

This anendment is effective as of the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISS10tl fr)

Darrell G. Eisenhut, Director Division of Licensing Office of Nuclear Reactor Regulation Date of Issuance: December 20, 1982

SEE ATTACHED PAGES FOR PREVIOUS CONCURRENCES

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) B.

Change paragraph 2.C.12.c to read as follows:

2.C.12 Environmental Qualifications (c) MP&L shall complete the following actions on schedules specified with each:

(1) Prior to exceeding 51, thermal power, flP&L shall implement the aging requirements specified in Section 3.7 and Section 4.3 of Appendix H of Supplement Ho. 2 of the Safety Evaluation Report.

(ii) Corrective actions for equipment identified in Exhibit B (Equipment Requiring Additional Information and/or Corrective Action) of Appendix H to Supplement 110. 2 of the Safety Evaluation Report shall be completed in-accordanceMttr-the ti me _ requi recents _ to - be -spec i f ied-i n-the-f i nal-10-CFR-50. 49 rul emak ing - on - enyi ronmentalmtua l i fi cati on. gj /4 d o #

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(iii) For equipment identified by MPLL in letters dated September 1, 1981, December 21, 1981, and April 8,1982, requiring either replacement or modification to justify interin operation, MP&L shall conalete this work prior to exceeding 5% thermal power.

3.

This arendment is effective as of the date of issuance.

FOR Tile NUCLEAR REGULATORY COPISSIO?!

Darrell G. Eisenhut, Director Division of Licensing Office of Nuclear Reactor Regulation i

Date of Issuance: November

, 1982 i

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See Attached page for previous concurrences.

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B.

Chage paragraph 2.C.12.c to read as follows:

2.C.12 Environmental Qualifications (c) MP&L shall complete the following actions on schedules specified with each:

(i) Prior to exceeding 5% thermal power, MP&L shall implenent the aging requirements specified in Section 3.7 and Section 4.3 of Appendix H of Supplement Ho. 2 of the Safety Evaluation Report.

(ii) Corrective actions for equipment identified in Exhibit B (Equipment Requiring Additional Information and/or Corrective Action) of Appendix H to Supplement No. 2 of the Safety Evaluation Reoort shall be completed in accordance with the time requirements to be specified in the final 10 CFR 50.49 rulemaking on environmental qualification.

(iii) For equipment identified by 11Pt.L in letters dated September 1, 1981, December 21, 1931, and April 8, 1982, requiring either replacement or redification to justify interim operation, MP&L shall complete this work prior to exceeding 5% thermal power.

3.

This anendment is effective as of the date of issuance.

FOR THE fiUCLEAR REGULATORY C0W11SS10!1 Darrell G. Eisenhut, Director Division of Licensing Office of Nuclear Reactor Regulation Date of Issuance: November

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ATTACHMENT TO LICENSE AMENDMENT NO. 5 FACILITY OPERATING LICENSE NO. NPF-13 DOCKET NO. 50-416 Replace the following page of the Appendix "A" Technical Specifications with the enclosed page. This revised page is identified by Amendment number and contains a vertical line indicating the area of change.

REMOVE INSERT 3/4 4-24 3/4 4-24 3/4 4-25 3/4 4-25 l

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REACTOR COOLANT SYSTEM 2

3/4.4.9 RESIDUAL HEAT REMOVAL HOT SHUTDOWN LIMITING CONDITION FOR OPERATION 3.4.9.1 Two# shutdown cooling mode loops of the residual heat removal (RHR) system shall be OPERABLE and, unless at least one recirculation pump is in operation, at least one shutdown cooling mode loop shall be in operation **##

with each loop consisting of at least:

a.

One OPERABLE RHR pump, and b '.

One OPERABLE RHR heat exchanger.

APPLICABILITY:

OPERATIONAL CONDITION 3, with reactor vessel pressure less than the RHR cut-in permissive setpoint.

ACTION:

a.

With less than the above requirec RHR shutdown cooling mode loops OPERABLE, immediately initiate corrective action to return the required loops to OPERABLE status as soon as possible. Within one hour and at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter, demonstrate the operability of at least one alternate method capable of decay heat removal for each inoperable RHR shutdown cooling mode loop.

Be in at least COLD SHUTDOWN within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .**

b.

With no RHR shutdown cooling mode loop in operation, immediately initiate corrective action to return at least one loop to operation as soon as possible. Within one hour establish reactor coolant circulation by an alternate method and monitor reactor coolant temperature and pressure at least once per hour.

SURVEILLANCE REQUIREMENTS 4.4.9.1 At least one shutdown cooling mode loop of the residual heat removal system or alternate method shall be determined 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 .

0ne RHR shutdown cooling mode loop may be inopsrable for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months fo'r surveillance testing provided the other loop is OPERABLE and in operation.

The shutdown cooling pump may be removed from operation for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months per 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months period provided the other loop is OPERABLE.

1. The RHR shutdown cooling mode loop may be removed from operation during hydrostatic testing.

- Whenever two or more RHR subsystems are inoperable, if unable to attain COLD SHUTDOWN as required by this ACTION, maintain reactor coolant temperature as j

low as practical by use of alternate heat removal methods.

GRAND GULF-UNIT 1 3/4 4-24 Anendment No. 5

REACTOR COOLANT SYSTEM COLD SHUTDOWN LIMITING CONDITION FOR OPERATION 3.4.9.2 Two# shutdown cooling mode loops of the residual heat removal (RHR) system shall be OPERABLE and, unless at least one recirculation pump is in operation, at least one shutdown cooling mode loop shall be in operation *'N with each loop consisting of at least:

l a.

One OPERABLE RHR pump, and b.

One OPERABLE RHR heat exchanger.

APPLICABILITY:

OPERATIONAL CONDITION 4.

ACTION:

a.

With less than the above required RHR shutdown cooling mode loops OPERABLE, within one hour and at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter, demonstrate the operability of at least one alternate method capable of decay heat removal for each inoperable RHR shutdown cooling mode loop.

b.

With no RHR shutdown cooling mode loop in operation, within one hour establish reactor coolant circulation by an alternate method and monitor reactor coolant temperature and pressure at least once per hour.

SURVEILLANCE REQUIREMENTS 4.4.9.2 At least one shutdown cooling mode loop of the residual heat removal system or alternate method shall be determined 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 .

0ne RHR shutdown cooling mode loop may be inoperable for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing provided the other loop is OPERABLE and in operation.

The shutdown cooling pump may be removed from operation for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months per 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months period provided the other loop is OPERABLE.

1. The shutdown cooling mode loop may be removed from operation during hydrostatic testing.

GRAND GULF-UNIT 1 3/4 4-25 Amendment No. 5

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ML20070K471

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