Text

Amends 103 & 133 to Licenses DPR-71 & DPR-62,respectively, Revising Tech Specs by Deleting nonsafety-related Instruments from Surveillance Requirements Re RCS Leakage & Leakage Detection Sys
	ML20212J362
Person / Time
Site:	Brunswick
Issue date:	01/21/1987
From:	Muller D; Office of Nuclear Reactor Regulation
To:	; Carolina Power & Light Co
Shared Package
ML20212J366	List: ML20212J362; ML20212J369;
References
	DPR-62-A-133, DPR-71-A-103 NUDOCS 8701280166
	Download: ML20212J362 (10)
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p '1 CAROLINA POWER & LIGHT COMPANY DOCKET N0. 50-325 BRUNSWICK STEAM ELECTRIC PLANT, UNIT 1 l

AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 103 License No. DPR-71 I.

1.

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

l A.

The application for amendment by Carolina Power & Light Company (the licensee) dated March 17, 1966, as supplemented October 13, l

1986 complies with the standards and requirements of the Atomic Energy l

Act of 1954, as amended (the Act) and the Commission's rules and i

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 I

ar.d safety of the public, and (ii) that such activities wil14 be conducted in compliance with the Connission'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 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-71 is hereby amended to read as follows:

8701280166 B70121

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PDR ADOCK 05000324 P

PDR i

. (2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendrrent No.103, 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 and shall be implemented within 60 days of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION O

p#ist. -

Daniel R. Muller, Director BWR Project Directorate #2 Division of BWR Licensing

Attachment:

Changes to the Technical Specifications Date of Issuance:

January 21, 1987 r

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ATTACHMENT TO LICENSE AMENDMENT NO. 103 FACILITY OPERATING LICENSE N0. DPR-71 DOCKET NO. 50-325 Repli.ce the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised areas are indicated by marginal lines.

Pages 3/4 4-5 3/4 4-6 l

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(BSEP-1-78)

REACTOR COOLANT SYSTIM 3/4.4.3 REACTOR COOLANT SYSTEM LEAKACE LEAKACE DETECTION SYSTEMS LIMITINC CONDITION FOR OPERATION 4

3.4.3.1 The following reactor coolant system leakage detection systems shall be OPERABLE:

The primary containment atmosphere particulate radioactivity a.

monitoring system,*

I l

b.

The primary containment sump flow integrating system, and L

The primary containment gaseous radioactivity monitoring system.*

c.

APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, and 3.

ACTION:

With only two of the above required leakage detection systems OPERABLE, y

operation may continue for up to 31 days provided grab samples of the containment atmosphere are obtained and analyzed at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when the required gaseous and/or particulate radioactive monitoring system is inoperable; otherwise, be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

i SURVEILLANCE REQUIREMENTS

?

k 4.4.3.1 The reactor coolant system leakage detection systems shall be

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demonstrated OPERABLE by:

I Primary containment atmosphere particulate and gaseous radioactivity a.

monitoring systems performance of a CHANNEL CHECK at least once per 3

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , a CHANNEL FUNCTIONAL TEST at least once per 31 days, and a CHANNEL CALIBRATION at least once per 18 months.

(CAC-AQH-1260-

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1,2,3; CAC-AQH-1262-1,2,3; CAC-AQH-1261-1,2,3) i b.

Containment sump flow integrating systems performance of a CHANNEL h

FUNCTIONAL TEST at least once per 31 days and of a CHANNEL f

CALIBRATION at leert once per 18 months.

(C16-FQ-K603; C16-FYQ-K603; C16-FQ-K601; C16-FYQ-K601; C16-FT-N013; C16-FT-N003) l l

The system is OPERABLE if one channel is OPERABLE.

I L

BRUNSWICK - UNIT 1 3/4 4-5 Amendment No. 76,103

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(BSEP-1-78)

REACTOR COOLANT SYSTEM OPERATIONAL LEAKACE LIMITING CONDITION FOR~0PERATION 3.4.3.2 Reactor coolant system leakage shall be limited to:

a.

No PRESSURE BOUNDARY LEAKACE.

b.

5 gpm UNIDENTIFIED LEAKAGE averaged over any 24-hour period.

c.

25 gpm total leakage averaged over any 24-hour period.

d.

2 gpm increase in UNIDENTIFIED LEAKACE within any 24-hour period except for the first 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months of reactor startup commencing with entry into OPERATIONAL CONDITION 2.

APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, and 3.

ACTION:

a.

With any PRESSURE BOUNDARY LEAKAGE, be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the next 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

b.

With any reactor coolant system leakage greater than any one of the above limits, excluding PRESSURE BOUNDARY LEAKAGE, reduce the leakage rate to within the limits withic. 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

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SURVEILLANCE REQUIREMENTS 4.4.3.2 The reactor coolant system leakage shall be demonstrated to be within each of the above limits by:

a.

Monitoring the drywell and equipment drain sump flow rates at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , and (C16-FQ-K603; C16-FYQ-K603; C16-FQ-K601; C16-FYQ-K601; C16-FT-N013; C16-FT-NOO3).

i b.

Monitoring the primary containment atmosphere particulate and gaseous k

radioactivity at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

(CAC-AQH-1260-1,2,3; l

CAC-AQH-1262-1,2,3 and CAC-AQH-1261-1,2,3).

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BRUNSWICK - UNIT 1 3/4 4-6 Amendment No. 76,103 F

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CAROLINA POWER & LIGHT COMPANY DOCKET NO. 50-324 BRUNSWICK STEAM ELECTRIC PLANT, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.133 License No. DPR-62 1.

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

A.

The application for amendment by Carolina Power & Light Company (the licensee) dated March 17, 1986, as supplemented October 13, 1986 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; f

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.

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-62 is hereby amended to read as follows:

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, (2) Technical Specifications I

The Technical Specifications contained in Appendices A and B, as

- revised through Amendment No.133, 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 and shall be implemented within 60 days of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION 44 Daniel R. Muller, Director BWR Project Directorate #2 -

Division of BWR Licensing

Attachment:

Changes to the Technical Specifications Date of Issuance:

January 21, 1987 I

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2 ATTACHMENT.TO LICENSE AMENDMENT NO.133-FACILITY OPERATING LICENSE NO. DPR-62 lDOCKETNO.50-324.

Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised areas are indicated by marginal lines.

Pages 3/4 4-5 3/4 4-6 4

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(BSEP-2-78)

REACTOR COOLANT SYSTEM 3/4.4.3 REACTOR COOLANT SYSTEM LEAKAGE LEAKACE DETECTION SYSTEMS t

LIMITING CONDITION FOR OPERATION 3.4.3.1 The following reactor coolant system leakage detection systems shall be OPERABLE:

The primary containment atmosphere particulate radioactivity a.

monitoring system,*

b.

The primary containment sump flow integrating system, and The primary containment gaseous radioactivity monitoring system.*

c.

APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, and 3.

ACTION:

With only two of the above required leakage detection systems OPERABLE, operation may continue for up to 31 days provided grab samples of the t

containment atmosphere are obtained and analyzed at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when the required gaseous and/or particulate radioactive monitoring system is inoperable; otherwise, be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

SURVEILLANCE REQUIREMENTS 4

4.4.3.1 The reactor coolant system leakage detection systems shall be demonstrated OPERABLE by:

Primary containment atmosphere particulate and gaseous radioactivity a.

monitoring systems performance of a CHANNEL CHECK at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , a CHANNEL FUNCTIONAL TEST at least once per 31 days, and a CHANNEL CALIBRATION at least once per 18 months.

(CAC-AQH-1260-1,2,3; CAC-AQH-1262-1,2,3; CAC-AQH-1261-1,2,3) l p

c b.

Containment sump flow integrating systems performance of a CHANNEL FUNCTIONAL TEST at least once per 31 days and of a CHANNEL CALIBRATION at least once per 18 months.

(C16-FQ-K603; C16-FYQ-K603; C16-FQ-K601; C16-FYQ-K601; C16-FT-N013; C16-FT-N003) t L

The system is OPERABLE if one channel is OPERABLE.

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BRUNSWICK - UNIT 2 3/4 4-5 Amendment No. 102, 133 h

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(BSEP-2-78) t REACTOR COOLANT SYSTEM OPERATIONAL LEAKAGE LIMITING CONDITION FOR OPERATION 3.4.3.2 Reactor coolant system leakage shall be limited to:

L a.

No PRESSURE BOUNDARY LEAKAGE.

b.

5 gpm UNIDENTIFIED LEAKAGE averaged over any 24-hour period.

25 gpm total leakage averaged over any 24-hour period.

c.

d.

2 gpm increase in UNIDENTIFIED LEAKAGE within any 24-hour period except for the first 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months of reactor startup commencing with entry into OPERATIONAL CONDITION 2.

APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, and 3.

ACTION:

With any PRESSURE BOUNDARY LEAKAGE, be in at least HOT SHUTDOWN a.

[

within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the next 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

b.

With any reactor coolant system leakage greater than any one of the i

above limits, excluding PRESSURE BOUNDARY LEAKAGE, reduce the leakage rate to.within the limits within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months or be in at least HOT i

SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

I

[

SURVEILLANCE REQUIREMENTS 1

4.4.3.2 The reactor coolant system leakage shall be demonstrated to be within each of the above limits by:

'e Monitoring the drywell and equipment drain sump flow rates at least i

a.

once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , and (C16-FQ-K603; C16-FYQ-K603; G16-FQ-K601;

{

C16-FYQ-K601; C16-FT-N013; G16-FT-N003).

ii b.

Monitoring the primary containment atmosphere particulate and gaseous i

radioactivity at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

(CAC-AQH-1260-1,2,3;

{

CAC-AQH-1262-1,2,3 and CAC-AQH-1261-1,2,3).

I I

BRUNSWICK - UNIT 2 3/4 4-6 Amendment No. 102, 133 l

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ML20212J362

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