Text

Amends 76 & 102 to Licenses DPR-71 & DPR-62,respectively, Revising Tech Specs 4.4.3.1.b & 4.4.3.2.a to Incorporate Changes in Instrument Tag Numbers
	ML20093C958
Person / Time
Site:	Brunswick
Issue date:	09/22/1984
From:	Vassallo D; Office of Nuclear Reactor Regulation
To:	; Carolina Power & Light Co
Shared Package
ML20093C961	List: ML20093C958; ML20093C964;
References
	DPR-62-A-102, DPR-71-A-076 NUDOCS 8410110019
	Download: ML20093C958 (17)
	v • d • e

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2 UNITED STATES

[*m,'_ i NUCLEAR REGULATORY COMMISSION 3

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CAROLINA POWER & LIGHT COMPANY DOCKET NO. 50-325 BRUNSWICK STEAM ELECTRIC PLANT, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 76 License No. DPR-71 1.

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

A.

The application for amendment by Carolina Power & Light Company (the licensee) dated May 10, 1984, as supplemented June 18, 1984 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 (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 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 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:

8410110019 840922 PDR ADOCK 05000324 p

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1

_2 2.

Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 76 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

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- n Domenic B. Vassallo, Chief Operating Reactors Branch #2 Division of Licensing

Attachment:

Changes to the Technical Specifications Date of Issuance: September 22, 1984 3

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I ATTACHMENT TO LICENSE AMENDMENT NO. 76 FACILITY OPERATING LICENSE NO. DPR-71 DOCKET NO. 50-325 Revise the Appendix A Technical Specifications as follows:

Remove Insert 3/4 1-12 3/4 1-12 3/4 3-42 3/4 3-42 3/4 4-5 3/4 4-5 3/4 4-6 3/4 4-6 3/4 6-25 3/4 6-25 3/4 6-26 3/4 6-26

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(BSEP-1-17)

REACTIVITY CONTROL SYSTEMS J

SURVEILLANCE REQUIREMENTS 4.1.3.7.1 The control rod reed switch position indicators shall be determined OPERABLE by verifying:

a.

At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , that the position of the control rod is indicated, b.

That the indicated control rod position changes during the movement of the control rod when performing Surveillance Requirement 1

4.1.3.1.2, and c.

That the control rod reed switch position indicator corresponds to the control rod position indicated by the " full-out" reed switches when performing Surveillance Raquirement 4.1.3.6.b.

4.1.3.7.2 When the'RSCS is required to be OPERABLE, the position and bypassing of control rods.with inoperable " Full-in" or " Full-out" reed switch position indication shall be verified by a second licensed operator or other 4

, qualified member of the technical staff.

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BRUNSWICK - UNIT 1 3/4 1-12 Amendment No. 76 m.~-p r-.--

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TABLE 3.3.4-2

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CONTROL. ROD WITHDRAWAL BLOCK INSTRUMENTATION SETPOINTS R

c:

TRIP FUNCTION AND INSTRUMENT NUMBER TRIP SETPOINT ALLOWABLE VALUE N

"8 1.

APRM (CSI-APRM-Cil. A,B,C,D,E,F) a.

Upscale (Flow Biased)

< (0.66W + 42%)

T*

< (0.66W + 42%)

T*

HTPF NTPF b.

Inoperative NA NA c.

Downscale

> 3/125 of full scale

> 3/125 of full scale d.

Upscale (Fixed)

[12%ofRATEDTHERMALPOWER

{12%ofRATEDTHERMALPOWER z

2.

ROD BLOCK HONITOR (Q51-RBM-CH.A.B) a.

Upscale

< (0.66W + 41%)

T*

< (0.66W + 41%)

T*

1 MTPF NTPF k'

b.

Inoperative NA NA '

j c.

Downscale

__ 3/125 of full scale

_ 3/125 of full scale B

]

3.

SOURCE RANCE MONITORS (C51-SRM-K600A,B,C.D) 1 a.

Detector not full in NA NA j

b.

Upscale

[ l x 10 cps j[ l x 105 cps c.

Inoperative NA NA d.

Downscale

> 3 cps

> 3 cps 4.

INTERMEDIATE RANCE MONITORS (C51-IRM-K601A B,C,D,E,F.C.It) a.

Detector not full in NA i

NA b.

Upscale j[108/125 of full scale

[108/125 of full scale c.

Inoperative NA NA d.

Downscale

> 3/125 of full scale

> 3/125 of full scale 5.

SCRAM DISCHARCE VOLUME (Cll-LSH-N013E)

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E.

a.

Water Level - High j[ 73 gallons j[ 73 gallons n"

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T=2.43 for 8x8 fuel T=2.39 for 8x8R fuel

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T=2.39 for P8x8R fuel 1

(BSEP-1-33)

REACTOR COOLANT SYSTEM 3/4.4.3 REACTOR COOLANT SYSTEM LEAKAGE LEAKAGE DETECTION SYSTEMS LIMITING CONDITION FOR OPERATION 3.4.3.1 The following reactor coolant system leakage detection systems shall be OPERABLE:

The primary containment atmosphere particulate radiosceivity l

a.

monitoring system,*

b.

The primary containment sump flow integrating system, and c.

The primary containment gaseous radioactivity monitoring system.*

APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, and 3.

l 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 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 4.4.3.1 The reactor coolant system leakage detection systems shall be l

demonstrated OPERABLE by:

a.

Primary containment atmosphere particulate and gaseous radioactivity l

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 C11ANNEL 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 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.

(G16-FQ-K603; G16-FYQ-K603; G16-FQ-K601; G16-FYQ-K601; G16-FY-K602; G16-FY-K600; G16-FT-N013; G16-FT-N003) l

The system is OPERABLE if one channel is OPERABLE.

BRUNSWICK - UNIT 1 3/4 4-5 Adendment No. 76 j

l' (BSEP-1-33)

REACTOR C00LAN"' SYSTEM OPERATIONAL LEAKAGE,.

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i LIMITING CONDITION FOR OPERATION 3.4.3.2 Reactor coolant system leakage shall be limited to:

a.

No PRESSURE BOUNDARY LEAKAGE.

b.

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

e.

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

d.

2 gpa increase in UNIDENTIFIED LEAKAGE within any 24-hour period i

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.

l APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, and 3.

l l

ACTION:

s.

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 within 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 .

. SURVEILLANCE REQUIREMENTS 4.4.3.2 The reactor coolant system leakage shall be demonstrated to be within i

each of the above limits by:

1 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 (G16-FQ-K603; G16-FYQ-K603; G16-FQ-K601; G16-FYQ-K601; G16-FY-K602; G16-FY-K600; G16-FT-N013; G16-FT-N003).

b.

Monitoring the primary containment atmosphere particulate and gaseous l

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).

4 I

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f BRUNSWICK - UNIT 1 3/4 4-6 Amendment No. 76

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(BSEP-1-17) 4 CONTAINMENT SYSTEMS

~3/4.6.6 CONTAINMENT ATMOSPHERE CONTROL STAND 8Y CAS TREATMENT SYSTEM LIMITING CONDITION FOR OPERATION 3.6.6.1 Two irdependeat standby gas treatment subsystems shall be OPERABLE.

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APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, 3, 5, and *.

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ACTION:

4 With one standby gas treatment subsystem inoperable:

s.

l 1.

In OPERATIONAL CONDITION 1, 2, or 3, restore the inoperable subsystem l

j to OPERABLE status within 7 days or be in at least HOT SHUTDOWN j

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 j

hours.

2.

In OPERATIONAL CONDITION 5 or *, restore the inoperable subsystem to l

OPERABLE status within 31 days or suspend irradiated fuel handling in I

the secondary containment, CORE ALTERATIONS, or operations that could reduce the SHUTDOWN MARGIN. The provisions of Specification 3.0.3 are not applicable.

]

b.

With both standby gas treatment subsystems inoperable; 1.

In OPERATIONAL CONDITION 1, 2, or 3, be in at least HOT SHUTDOWN l

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 .

2.

In OPERATIONAL CONDITION 5 or *, suspend all irradiated fuel handling l

in the secondary containment, CORE ALTERATIONS, or operations that could reduce the SHUTDOWN MARGIN. The provisions of Specification

]

3.0.3 are not applicable.

I SURVEILLANCE REQUIREMENTS i

l 4.6.6.1 Each standby gas treatment subsystem shall be demonstrated OPERABLE:

a.

At least once per 31 days by initiating, from the control room, flow g

i through the HEPA filters and charcoal absorbers, and verifying that l

the subsystem operates for at least 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months with the heaters on l

automatic control.

l b

When irradiated fuel is being handled in the secondary containment.

BRUNSWICK - UNIT 1 3/4 6-25 Amendment No. 76 s

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, CONTAI19 TENT SYSTEMS SURVEIT2.ANCE REQUIREMENTS (Continued) b.

At least once per 18 months or (1) af ter any structural maintenance on the HEPA filter or charcoal abcorber housings, or (2) following painting, fire or chemical release in any ventilation zone, 4

i communicating with the system by:

1 1.

Verifying that the cleanup system satisfies the in-place testing acceptance criteria and uses the test procedures of Regulatory Positions C.5.a., C.5.c, and C.S.d of Regulatory Guide ~1.52, Revision 1, July 1976, and the system flow rate is 3000 cfm +

10%.

2.

-Verifying within 31 days af ter removal that a laboratory analysis of a representative carbon sample obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 1, July 1976, meets the laboratory testing criteria of Regulatory Position C.6.a of Regulatory Guide 1.52, Revision 1, July 1976.

3.

Verifying a system flow rate of 3000 cfm + 10% during system operation when tested in accordance with ANSI N510-1975.

After every 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months of charcoa1 absorber operation by verifying c.

within 31 days after removal that a laboratory analysis of

~

representative carbon sample obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 1, July 1976, meets l

the laboratory testing criteria of Regulatory Position C.6.a of Regulatory Guide 1.52, Revision 1, July 1976.

d.

At least once per 18 months by:

1.

Verifying that the pressure drop across the combined REPA filters and charcoal absorber banks is less than 8.5 inches l

Water Gauge while operating the filter train at a flow rate of 3000 cfm _+ 10%.

2.*

Verifying that.the filter train starts on each secondary containment isolation test signal.

3.

Verifying that the heaters will dissipate at least 15.2 kw when tested in accordance with ANSI N510-1975.

Fo*

the performance of this surveillance scheduled to be completed by February 25, 1981, a onetime-only exemption is allowed to extend this surveillance until "before the completion of the Spring 1981 outage,"

scheduled to commence in March, 1981.

BRUNSWICK - UNIT 1 3/4 6-26 Amendment No. 76 i

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/ merg*o, UNITED STATES E3 77, NUCLEAR REGULATORY COMMISSION 4

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CAROLINA POWER & LIGHT COMPANY I

DOCKET NO. 50-324 4

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BRUNSWICK STEAM ELECTRIC PLANT, UNIT 2 AMENDMENTTOFACILITYOPERATINGLIdENSE

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Amendment No.102 License No. DPR-62 1.

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

A.

The application for amendment by Carolina Power & Light Company (thelicensee)datedMay 10, 1984, as supplemented June 18, 1984 complies with the standards and re Act of 1954, as amended (the Act) quirements of the Atomic Energy 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 (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 l

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-62 is hereby amended to read as follows:

. l 2.

Technical Specifications s

The Technical Specifications contained in Appendices A and B, as iI revised through Amendment No.102, 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 I

DomenicB.hassallo, Chief Operating Reactors Branch #2 l

Division of Licensing l

Attachment:

Changes to the Technical Specifications Date of Issuance: September 22, 1984

~

i

ATTACHMENT TO LICENSE AMENDMENT NO.102 i

FACILITY OPERATING LICENSE NO. DPR-62 DOCKET NO. 50-324 Revise the Appendix A Technical Specifications as follows:

Remove Insert 3/4 1-12 3/4 1-12

-3/4 4-5 3/4 4-5 3/4 4-6 3/4 4-6 3/4 6-25 3/4 6-25 3/4 6 3/4 6-26 1

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(BSEP-2-17)

REACTIVITY CONTROL SYSTEMS r

LIMITING CONDITION FOR OPERATION (Continued) b.

In CONDITION 5* with a withdrawn control rod reed switch position indicator inoperable, fully insert the withdrawn control rod. The provisions of Specification 3.0.3 are not applicable.

~ SURVEILLANCE REQUIREMENTS 4.1.3.7.1 The control rod reed switch position indicators shall be determined OPERABLE by verifying:

a.

At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , that the position of the control rod is indicated, b.

That the indicated control rod position changes during the movement of the control rod when performing Surveillance Requirement 4.1.3.1.2, and c.

That the control rod reed swith position indicator corresponds to the l

control rod position indicated by.the " Full-out" reed switches when performing Surveillance Requirement 4.1.3.6.b.

i 4.1. 3. 7. 2 When the RSCS is required to be OPERABLE, the position and bypassing of control rods with ir. operable " Full-in" or " Full-out" reed switch position indication shall be verified by a second licensed operator or other qualified member of the technical staff.

l 6

I

At least each withdrawn control rod.

Not applicable to control rods removed per Specification 3.9.10.1 or 3.9.10.2.

I i

i BnUNSNICK-UNIT 2 3/4 1-12 Amendment No.102

~

(BSEP-2-33) 4 a.

REACTOR COOLANT SYSTEM 3/4.4.3 REACTOR COOLANT SYSTEM LEAKAGE LEAKAGE DETECTION SYSTEMS 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 l

a.

monitoring system,*

b.

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

c.

I I

APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, and 3.

l 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 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 4.4.3.1 The reactor coolant system leakage detection systems shall be l

demonstrated OPERABLE by:

Primary containment atmosphere particulate and gaseous radioactivity l

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 b.

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

(G16-FQ-K603; G16-FYQ-K603;

~

G16-FQ-K601; G16-FYQ-K601; G16-FY-K602; G16-FY-K600; G16-FT-N013; G16-Pf-N003)

The system is OPERABLE if one channel is OPERABLE.

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

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(BSEP-2-33) r.

REACTOR COOLANT SYSTFM OPERATIONAL LEAKAGE LIMITING CONDITION FOR OPERATION 3.4.3.2 Reactor coolant' system leakage shall be limited to:

a.

No PRESSURE BOUNDARY LEAKAGE.

b.

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

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

c.

d.

2 gym 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 comeencing with entry into OPERATIONAL CONDITION 2.

l APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, and 3.

l ACTION:

i 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 .

i b.

With any reactor coolant system leakage greater than any one of the above limits, excluding PRESSURE BOUNDARY LEAKAGE, reduce the leakage 1

race 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 SHUTDOWN within the nexc 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 4.4.3.2 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 (G16-FQ-K603; G16-FYQ-K603; G16-FQ-K601; G16-FYQ-K601; G16-FY-K602; G16-FY-K600; G16-FT-N013; G16-FT-N003).

i b.

Monitoring the primary contain:nent atmosphere particulate and gaseous radioactivity at ledst 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-l,2,3 and CAC-AQH-1261-1,2,3).

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I I

J-i BRUNSWICK - UNIT 2 3/4 4-6 Amendment No.102 1

(BSEP-2-17)

CONTAINMENT SYSTEMS 3/4.6.6 CONTAINMENT ATMOSPHERE CONTROL STANDBY CAS TREATMENT SYSTEM LDMITING CONDITION FOR OPERATION 3.6.6.1 Two independent standby gas treatment subsystems shall be OPERABLE.

l APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, 3, 5, and *.

l ACTION:

a.

With one standby gas treatment subsystem inoperable:

1.

In OPERATIONAL CONDITION 1, 2, or 3, restore the inoperable l

sybsystem to OPERABLE status within 7 days 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 .

2.

In OPERATIONAL CONDITION 5 or *, restore the inoperable subsystem to l

OPERABLE status within 31 days or suspend irradiated fuel handling in the secondary containment, CORE ALTERATIONS, or operations that could reduce the SHUTDOWN MARGIN. The provisions of Specification 3.0.3 are not applicable.

b.

With both standby gas treatment subsystems inoperable; 1.

In OPERATIONAL CONDITION 1, 2, or 3, be in at least HOT SHUTDOWN l

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 .

2.

In OPERATIONAL CONDITION 5 or *, suspend all irradiated fuel l

handling in the secondary containment, CORE ALTERATIONS, or operations that could reduce the SHUTDOWN MARGIN.' The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.6.6.1 Each standby gas treatment subsystem shall be demonstrated OPERABLE:

a.

At least once per 31 days by iniciating, from the control room, flow 3', i through the HEPA filters and charcoal adsorbers and verifying that t

the subsystem operates for at least 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months with the heaters on j

automatic control.

t

When irradiated fuel is being handled in the secondary containment.

\\ i F

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c' 1

N BRUNSWICK - UNIT 2 3/4 6-25 Amendment No. 102 0

.,_ r r

(BSEP-2-17)

- m,;.

m CONTAINMEkTSYSTEMS SURVII I.ANCE REQUIREMENTS (Cont!.nued) b.'

At least once per 18 months 'or (1) af ter any structural maintenance y

on the REPA filter or charcoal adsorber housings, or (2) following painting, fire..or< cherJeal release in any ventilation zone g,

communicating with\\the system by:

\\

i

~

1.

Verifying that the cleanup system satisfies the in place testing acceptance. criteria and uses the test procedures of

,.T~t -

Regulatory Positions C.S.a. C.S.c, and C.S.d of Regulatory j.

/ /

Guide 1.52, Ra' vision 1,' July 1976, and the system flow rate is 3000 cfm j; 10%.

1 Verifying'Eithin 31 days af ter removal that a laboratory 2.

4 analysis'of a representative carbon sample obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 1. July 1976, meets the laboratory testieg criteria of Regulatory Position C.6.a of Regula-tory Guide 1.52, Revision 1, July 1976.

3.

Verifying a system flow rate of 3000 cfm j; 10% during system operation when tested in accordance with ANSI N510-1975.

r After every 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months of charcoal adsorber operation by verifying within c.

31 days af ter removal that a laboratory analysis of representative carbon sample obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 1, July 1976, meets the laboratory j

testing criteria of Regulatory Position C.6.a of Regulatory Gaide 1.52, Revision 1, July 1976.

d.

At least once per 18 months by:

1.

Verifying that the pressure drop across the combined REPA filters and charcoal adsorber banks is less than 8.5 inches Water Gauge l

while operating the filter train at a flow rate of 3000 cfm j; 10%.

2.

Verif;<ing that the filter train starts on each secondary containment isolation test signal.

3.

Verifying that the heaters will dissipate at least 15.2 kw when tested in accordance with ANSI N510-1975.

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BRUNSWICK - UNIT 2 3/4 6-26 Amendment No. 102

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ML20093C958

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