Text

Amend 35 to License DPR-71,modifying Tech Specs to Permit Operation W/One Recirculation Loop Out of Svc
	ML19350D149
Person / Time
Site:	Brunswick
Issue date:	03/27/1981
From:	Ippolito T; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML19350D150	List: ML19350D149; ML19350D153;
References
	NUDOCS 8104130556
	Download: ML19350D149 (11)
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UNI TED STATES g

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NUCLEAR REGULATORY COMMISSION

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)'~ 7-s% -f E WASHINGTON, D. C. 20555 CAROLINA POWER & LIGHT COMPANY-DOCKET NO. 50-325 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 35 Li, cense No. DPR-71 1.

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

A.

The application for amendment by Carolina Power & Light Company cated March 5,1981, with supplement dated March 13, 1981, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Cocraission's rules and regulctions 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 Crmmission; C.

There is reasomble 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.

Tne issuance of this amendnent 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 amendnent 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-71 is hereby amended to read as follows :

(2)

Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.35, are hereby incorporated in the license.

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

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. 3.

This license amendment is effective as of March 5,1981.

FOR THE NUCLEAR REGULATORY COMMISSION 0<-Q:74 Thomas A. Ippolito, Chief Operating Reactors Branch #2 Division of Licensing A-ta chmen t:

CF.anges to the Technical Specifications Date of Issuance: March 27,1981.

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. ATTACHMENT TO LICENSE AMENDMENT N0.35 FACILITY OPERATING LICENSE NO. DPR-71 DOCKET NO. 50-325 Replace the.following pages of the Appendix "A" Technical Specifications with the enclosed pages.

The revised pages are identified by Amendment number'and contain vertical lines indicating the area of change.

Remove 3/4 2-1 / 3/4 2-2 3/4 2-7 / 3/4 2-8 i

3/43-41/3/43-42 3/4 4-1 / 3/4 4-2 i

The underlined pages are those being changed.

Overleaf pages are provided for convenience.

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o 3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 AVERAGE PLANAR LINEAR HEAT GENERATION RATE LiHITING CONDITION FOR OPERATION 3.2.1 ALL AVERAGE PLANAR LINEAR HEAT GENERATION RATES (APLHGR's) for each type of fuel as a function of AVERAGE PLANAR EXPOSURE shall not exceed the limits shown in Figures 3. 2.1 -1, 3.2.1 -2, 3.2.1 -3, 3. 2.1 -4, 3.2.1 -5 or

3. 2.1 - 6.

APPLICABILITY:

CONDITION 1, when THERMAL POWER > 25% of RATED THERN4L POWER.

ACTION:

With an APLHGR exceeding the limits of Figure 3.2.1-1, 3.2.1-2, 3.2.1-3, 3.2.1-4, 3.2.1-5 or 3.2.1-6, initiate corrective action within 15 minutes and continue corrective action so that APLHGR is within the limit within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months or reduce THERMAL POWER to less than 25% of RATED THERMAL POWER within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

S'JRVEILLANCE EEQUIREMENTS 4.2.1 All APLHGR's shall be verified to be equal to or less than the appli-cable limit determined from Figure 3.2.1 -1, 3.2.1 -2, 3. 2.1-3, 3.2.1-4, 3.2.1-5 or 3.2.1-6:

a.

At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , b.

Within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after completion of a THERMAL POWER increase of at least 15% of RATED THERMAL POWER, and Initially and at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months when the reactor is c.

operating with a LIMITING CONTROL R00 PATTERN for APLHGR.

"In single reactor recirculation loop operation, the APLHGR limit shall be reduced to.65 of the values specified in the above tables.

This portion of the Specification expires en March 15, 1981.

ER;NSWICX-UNIT 1 3/4 2-1 Amendment No. 35 l

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RODR ORIGINAL 3/4.2.2 APRM SETPOINTS LIMITING CONDITION FOR OPEPATION The flow biased APRM scram trip setpoint (S) and rod block tr'ip set 3.2.2 point (Sgg) snall be established according to the following relationship:

l S 1 (.0.66W + 54%) T S 3 (0.66W + 50.75) (Single Loop)*

pg 1 (0.66W + 38.M) (Single Loop)*

S 1 (0.66W + 42%) T S

R3 S and S.0 are in percent of PATED THERPAL POWER.

where:

W = Leop recirculation flow in percentor of rated flow.

T = Lowest value of the ratio of design TPF divided by the HTPF -

obtained for any class of fuel in the core (T 1 1.0),and Design TPF for:

8 x 8 fuel = 2.45.

8 x SR fuel = 2.48.

PB x SR fuel = 2.48.

APPLICABILITY:

CONDITION 1, when THER!GL POWER > 25% of RATED THERMAL POWER.

ACTION:

RB exceeding the allowable value, initiate corrective action within With 5 or S 15 minutes and continue corrective action so that S and Sgg are within~ the required limits within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months or reduce THERIGL POWER to less than 25% of FATED THEU'AL POWER within the next 4' hours.

SURVEILLA';CE RECUIREMENTS The MTPF for each class of fuel shall be determined, the value of T 4.2.2 calculated, and the flow biased APRM trip setpoint adjusted, as required:

a.

At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months af ter completion of a THERVAL POWER increase of at b.

least 15% of RATED THERMAL POWER, and Initially and at least once per 12 hcurs when the reactor is c.

operating with a LIMITING CONTROL R00 PATTERN for MTPF.

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This portion of the specification exp' ires on March 15, 1981.

ERUSSi.*iCK-UNIT 1 3/4 2-8 Amen h h M I

O P90R ORIGINAL TABLE 3.3.4-1 (Continued)

CONTROL ROD WITHDRAWAL BLOCK INSTRUMENTATION NOTE Uhen THER!!AL POWER exceeds the preset power level of the RhH and RSC5.

a.

The minimum number of OPERABLE CHANNELS may be reduced by one for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months in one of the trip systems for mairienance and/or test'ing except for Rod Block Mcnitor function.

b.

This function is bypassed if detector is reading > 100 cps or the IRM channels are on range 3 or higher.

c.

This function is bypassed when the associated IR!i channels are on range 8 or higher.

d.

A total of 6 IRM instrumencs must be OPEPAELE.

e.

This function is bypassed when the IRM channe's are on range 1.

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TRIP FU;1CT10fl A?;D lilSTRUMEf!T fiUMBER TRIP SETPOINT ALLOWAL E VALUE

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Downscale

> 3/125 of full scale

> 3/125 of full scale d.

Upscale (Fixed) 712% of RATED TilERMAL POWER 712% of RATED TilERMAL POWER 2.

R00 BLOCK MONITOR (C51-RDM-Cil.A,8) a.

Updcale 1(0.66W + 41%)

T* ***

1(0.66W + 41%)

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Inopera tive NA NA c.

Downscale

> 3/125 of full scale

> 3/125 of full scale 3.

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> 3 cps 4.

IrlTERMEDIATE RANGE MONITORS (C51-IRM-X601A,8,C,D,E,F,G,II) a.

Octcctor not full in NA NA b.

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< 108/125 of full scale c.

Inoperative NA NA d.

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> 3/125 of full scale "T=2.43 for llx8 fuel li!

l=2.4H for Ox8R' fuel E.

T=2.48 for P8x8R fuel n

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*When in single loop, trip setpoint and allowable value shall be reduced to < (.66W + 38.7%)

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hours in single recirculation loop operation. This Specification expires oii March 15,1981. MTPF F

"When in single loop, trip setpoint and allowable value shall be reduced to 1 (.66W + 35.7%)

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within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months in single recirculation loop operation.

MIPF m

This Specification expires on March 15, 1981.

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3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 RECIRCULATION SYSTEM F.ECIRC'JLATION LOOPS LIMITING CCNDITION FOR OPERATION 3.4.1.1 Two reactor coolant recirculation loops shall be in operation with tne cross-tie valve closed, the pump discharge valves OPERABLE and the pump discharge bypass valves OPERABLE or closed.

A?pLICABILITY:

CONDITIONS 1" and 2*.

ACTION:

With one or both recirculation loops not in operation, operation may ccntinue; restore both loops to operation within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months or be in at least EDT SHUTDOWN uithin the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .**

l S'_%VEILLANCE REOUIREMENTS

.:. 4.1.1 Each pump discharge valve and bypass valve shall be demonstrated CDER*5LE by cycling each valve through at least one complete cycle of full travel during each COLD SHUTDOWN which exceeds 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months , if not performed in the previous 31 days.

4.4.1.2 Each pump discharge bypass valve, if not OPER4SLE, shall be verified to be closed at least once per 31 days.

'See Special Test Exception 3.10.a.

"Until March 15, 1981, with one recirculation pump not in cperaticn, reduce p:wer to less than 50% and reduce the setpoints as specified in Table 2.2.1-1, Table 3.3.4-2, Section 3.2.1, and Section 3.2.2, within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

With both recirculation icops, not in operation, operation may continue; restore at least ene loop to operation within 12 hot.rs 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 .

E:J;.';5 WICK-UNIT i 3/c 4-1 Amendmer.t No. 35

P00R ORIGINAL ei REACTOR COOLANT SYSTEM t

JET PUMPS LIMI'!NG CONDITION FOR CPERATION

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3.4.1.2 All jet pumps shall be OPEF.A5LE.

APPLICA5:LITY:

CONDITIONS 1 and 2.

ACTION:

's'ith less than 20 jet pumps OPERAELE, be in at leas: HOT SHUTDOWN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

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SURVEILLANCE REOUIREMENTS

'4.4.1.2.Each of.the above required jet pumps shall be demonstrated OPERABLE prior to THEF.v.AL POWER exceeding 25% of RATED THEF.".AL POWER and at least ence per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by verifying that all of the following c:nditions do not Oc:ur simultaneously.

a.

The recirculation pump ficw differs by more than 10% from -

the established speed-flow characteristics, b.

The indicated total core flew differs by more than'10% from the core flow value derived from established power-core flow relationships, and c.

The diffuser-to-lcwer plenum differential pressure reading on any individual jet pump varies from the mean cf all jet pump differential pressures, in that loop, by more than 10t i

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ML19350D149

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