Text

Amends 216 & 185 to Licenses DPR-62 & DPR-71,respectively, Incorporating New TS for Instrumentation Associated W/Automatic Isolation of Pathway for Release of Noncondensible Gases from Main Condenser
	ML20141A811
Person / Time
Site:	Brunswick
Issue date:	05/09/1997
From:	Reinhart M; NRC (Affiliation Not Assigned)
To:	;
Shared Package
ML20141A816	List: ML20141A811; ML20141A840;
References
	NUDOCS 9705150020
	Download: ML20141A811 (24)
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UNITED STATES y

j NUCLEAR REGULATORY COMMISSIOP p

WASHINGTON, D.C. eamma anny

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CAROLINA POWER & LIGHT COMPANY. et al.

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DOCKET NO. 50-325 BRUNSWICK STEAM ELECTRIC PLANT. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.185 License No. DPR-71 11.

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

1

'A.

The application for amendment filed by Carolina Power & Light j

Company (the licensee), dated March 5, 1997, as supplemented May 9, 1997,. complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the i

Commission's rules and regulations set-forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the i

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 i

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:

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9705150020 970509 PDR ADOCK 05000324 P

PDR

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Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.185, are hereby incorporated in the license. Carolina Power & Light Company 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 prior to the next reactor startup requiring operation of the condenser vacuum pump, but no later than the end of refueling outage 11 (B112RI).

FOR THE NUCLEAR REGULATORY COMMISSION k[(#W Mark hart Acting Director Project Directorate 11-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance:

May 9,1997

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ATTACHMENT TO LICENSE AMENDMENT NO.185 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 areas are indicated by marginal lines.

i Remove Phaes Insert Paaes V

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X 3/4 3-97 3/4 3-98 B3/4 3-6 B3/4 3-6 B3/4 3-7 B3/4 3-8 83/4 3-9 B3/4 3-10 9

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M LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS

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SECIIGl PKaE

]j 3/4.3 INSTRLMENTATION t

3/4.3.1 REACTOR PROTECTION SYSTEM INSTRLE NTATI0N..................

3/4 3-1

3 1

3/4.3.2 ISOLATION ACTUATION INSTRlNENTATION........................

3/4 3-10 4

j 3/4.3.3 EERGENCY CORE COOLING SYSTEM ACTUATION INSTR 1 MENTATION.... 3/4 3-33 3/4.3.4 CONTROL R0D WITIERAWAL BLOCK INSTRlMENTATION...............

3/4 3-47

>i' 4 3/4.3.5 MONITORING INSTRlMENTATION Seismi: Monitoring Instrumentation.........................

3/4 3 53 I

J-9l Remote Shutdown Monitoring Instrtmentation................. 3/4 3-56 qb(

Accident Monitoring Instrumentation........................

3/4 3 59 Source Range Monitors.....................................

3/4 3-63 j,

Control Room Emergency Ventilation System.................. 3/4 3-64 t

l-Chloride Intrusion Monitors................................

3/4 3-65 Fire Detection Instrtmentation (Deleted)................... 3/4 3-69 I

Radioactive Liquid Effluent Monitoring Instrtmentation..... 3/4 3-72 Radioactive Gaseous Effluent Monitoring Instrumentation.... 3/4 3-78 3/4.3.6 ATWS RECIRCULATION PlMP TRIP (RPT) SYSTEM INSTRlN NTATION.. 3/4 3-88

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i 3/4.3.7 REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION i

INSTRUMENTATION.........................................

3/4 3 92

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3/4.3.8 CO.NDENSER VACUUM PLMP ISOLATION INSTRUMENTATION............

3/4 3-97 1 I'

3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 RECIRCULATION SYSTEM

) jl Reci rcul ati on loop's........................................ 3/4 4-1 Jet Pumps..................................................

3/4 4-2 Idle Recirculation Loop Start-up............................

3/4 4-3 3/4.4.2 SAFETY / RELIEF VALVES.......................................

3/4 4-4 3/4.4.3 REACTOR COOLANT SYSTEM LEAKAGE Leakage Detection Systems.............

3/4 4-5 c

Operational Leakage........................................

3/4 4-6 h NIT 1 V

Amendnent No.185

BRUNSWICK U

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INDEX 1

l, BASES j

1 Ij SECTION P.8GE b.

3/4.0 APPLICABILITY..............................................

B 3/4 0-1 3/4.1 REACTIVITY CONTROL SYSTEMS t

3/4.1.1 SHUTDOWN MARGIN..........................................

B 3/4 1-1 i

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3//.1.2 REACTIVITY AN0MALIES.....................................

B 3/4 1-1 j

4 :i h

1 2: ;.3 CONTROL R00S.............................................

B 3/4 1-1 l

i 1

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3/4.1.4 CONTROL R00 PROGRAM CONTR0LS.............................

B 3/4 1-3 f.pj 3/4.1.5 STANDBY LIQUID CONTROL SYSTEM............................

B 3/4 1-4 I

l 3/4.2 POWER DISTRIBUTION LIMITS l

3/4.2.1 AVERAGE PLANAR LINEAR HEAT GENERATION RATE...............

B 3/4 2-1 i

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c 3 /4.2.2 MINIMLN CRITICAL POWER RATI0.............................

B 3/4 2-2 1

3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR PROTECTION SYSTEM INSTRlNENTATION................

B 3/4 3-1 3/4.3.2 ISOLATION ACTUATION INSTRlNENTATION......................

B 3/4 3-2 i

3/4.3.3 EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRlNENTATION..

B 3/4 3-2 i

L 3/4.3.4 CONTROL R00 WIT 10RAWAL BLOCK INSTRUMENTATION.............

B3/4 3-2a l

i 3/4.3.5. MONITORING INSTRUMENTATION...............................

B3/4 3-2a I

e 3/4.3.6 A1VS RECIRCULATION PUMP TRIP SYSTEM INSTRUMENTATION......

B 3/4 3 6 j

3/4.3.7 REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION i

INSTRLNENTATION.......................................

B 3/4 3-6 I

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3/4.3.B CONDENSER VACUlH PLNP ISOLATION INSTRUMENTATION..........

B 3/4 3 6 I f'

3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 RECIRCULATION SYSTEM.....................................

B 3/4 4-1 3/4.4.2 SAFETY / RELIEF VALVES.....................................

B 3/4 4-1 3/4.4.3 REACTOR COOLANT SYSTEM LEAXAGE..........................

B 3/4 4-1 a

BRUNSWICK UNIT 1 X

Amendnent No.185

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INSTRUMENTATION d

3/4.3.8 CONDENSER VACULN Plw ISOLATION INSTRlM NTATION

j LIMITING CONDITION FOR OPERATION

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3.3.8 Four channels of the Main Steam Line Radiation High Function for the

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condenser vacum ) ump isolation shall be OPERABLE with its trip setting set h

consistent with tw required Allowable Value.

APPLICABILITY:

OPERATIONAL CONDITIONS 1 and 2 with a condenser vacuum pu g in service.

I ACTION

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a. With one or more channel (s) of the Main Steam Line Radiation-High Function for condenser vacutsn pump isolation inoperable:

j; 1.

Restore channel to OPERABLE status within 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months s: or s

2.

Place channel or associated trip system in trip within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

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Otherwise: 1solate the condenser vacuum pinps, or isolate the main steam

1, lines, or be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

b.

With condenser vacutsn pump isolation capability not maintained:

l 1.

Isolate the condenser vacuum pinps within 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months s: or 2.

Isolate the main steam lines within 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months s: or 1

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3.

Be in HOT SHUTDOWN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

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c. When a channel is placed in an inoperable status solely for the i

performance of required Surveillances entry into associated Actions l

may be delayed for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months provided condenser vacuum pump isolation capability is maintained.

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Not applicable if the inoperable channel is the result of an inoperable condenser vacuum pump trip breaker or isolation valve.

BRUNSWICK - UNIT 1 3/4 3 97 Amendment No.185 l

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i INSTRUMENTATION 3/4.3.8 CONDENSER VACt1H PlNP ISOLATION INSTRtNENTATION i

SURVEILLANCE REQJIREMENTS i

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4.3.8 Each channel of the Main Steam Line Radiation-High Function for

' !.j condenser vacuum pump isolation shall be demonstrated OPERABLE by:

a.

Perfonnance of a CHANNEL CHECK at least once per 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months s:

1 b.

Performance of a CHANNEL FUNCTIONAL TEST at least once per 92 days:

c. Perfonnance of a CHANNEL CALIBRATION at least once per 18 months.

the Allowable Value shall be s 6 x background; and d.'

Perfonnance of a LOGIC SYSTEM FUNCTIONAL TEST, including condenser vacutsn plap trip breaker and isolation valve actuation, at least

~i once per 18 months.

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BRUNSWICK - UNIT 1 3/4 3-98 Anendnent No.185 l i

1 INSTRlMENTATION

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BASES 3/4.3.6 ATWS RECIRClLATION PtNP TRIP ACTUATION INSTRtNENTATION 3

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The ATWS recirculation p trip system has been added at the suggestion of ACRS as a means of limit the consequences of the unlikely occurrence of a

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failure to scram during an anticipated transient. The response of the plant i 1 to this )ostulated event falls within the envelope of study events given in l,

General Electric Conpany Tropical Report NED0-10349, oated March, 1971.

3 Specified surveillance intervals and allow! out-of-service times were established based on the reliability analyses documented in GE report

's GENE-770 06-1-A. " Bases for Changes to Surveillance Test Intervals and Allowed Out-of-Service Times for Selected Instrumentation Technical Specifications,"

j December 1992.

i 3/4.3.7 REACTOR CORE ISOLATION COOLING SYSTEM ACTllATION INSTRlNENTATION The reactor core isolation cooling system actuation instrtmentation is provided to initiate actions to assure adequate core cooling in the event of reactor isolation from its primary heat sink and the loss of feedeter flow to the reactor vessel without providing actuation of any of the emergency core cooling equipment.

Specified surveillance intervals and allowed out-of-service times were established based on the reliability analyses documented in GE report GENE-770-06-2P-A. " Bases for Changes to Surveillance Test Intervals and Allowed Out-of-Service Times for Selected Instrtmentation Technical

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Specifications," Decenber 1992.

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3/4.3.8 CONDENSER VACUlN P!NP ISOLATION INSTRlNENTATION Backaround The condenser vacuin pump isolation instrumentation initiates a trip of the respective rondenser vacuum purro and the common isolation valve following events in which the main steam line radiation monitor (s) exceed a predetermined value. The condenser vacuum pump isolation instrumentation initiates an isolation of the condenser vacuum pump (s) to limit main control

'.4 room doses resulting from fuel cladding failure in the event of a control rod drop accident (CRDA). The isolation logic consists of two inde>endent trip systems, with two channels of the Main Steam Line Radiation-Hig1 Function in each trip system. Each trip system is a one-out-of-two logic for this 1

Function. Thus, either channel of the Main Steam Line Radiation-High Function in each trip system are needed to tri) a tri) system. The outputs of the channels are arranged in a logic so tlat bot 1 trip systems must trip to result in an isolation signal.

i BRLNSWICK - UNIT 1 B 3/4 3 6 Amendnent No.185 l

l INSTRlNENTATION BASES q

3/4.3.8 CONDENSER VACulN PtNP ISOLATION INSTRlNENTATION (continued)

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The OPERABILITY of the condenser vacu m p m p isolation is dependent on the OPERABILITY of the individual Main Steam Line Radiation-High Function instrument channels, which must have its setpoint within the specified Allowable Value of Surveillance Requirement 4.3.8.c.

The actual setpoint is calibrated consistent with applicable setpoint methodology assaptions.

Channel OPERABILITY also includes the condenser vacuum pump trip breaker and isolation valve.

Acolitahility The condenser vacuum pump isolation is required to be OPERABLE in OPERATIONAL l9 CONDITIONS 1 and 2 when a condenser vacuum pump is in service, to mitigate the consequences of a postulated control rod drop accident. In this condition, l

fission products released during a control rod drop accident could be discharged directly to the environment. Therefore, the condenser vacum pump isolation is necessary to assure confonnance with tN radiological evaluation

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of the control rod drop accident.

In OPERATIONAL CONDITIONS 3, 4, or 5 the j

consequences of a control rod drop are insignificant and are not expected to i

result in any fuel damage or fission product releases. When a condenser vacum pung is not in operation in OPERATIONAL CONDITIONS 1 or 2, fission

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product releases via this pathway would not occur.

ACTION a.

With one or more channels inoperable, but with condenser vacum pm p isolation i

capability maintained (refer to ACTION b. Bases), the condenser vacuum pump isolation instrumentation is capable of performing the intended function.

However, the reliability and redundancy of the condenser vacum pump isolation j

instraentation is reduced, such that a single failure in one of the remaining channels could result in the inability of the condenser vacum ptmp isolation

.I instraentation to perform the intended function. Therefore, only a limited i

time is allowed to restore the inoperable channels to OPERABLE status.

j 4

Because of the low probability of extensive numbers of inoperabilities affecting multiple channels, and the low probability of an event requiring the 1

initiation of condenser vacu m pump isolation, 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months has been shown to be 4

acceptable (Ref.1) to permit restoration of any inoperable channel to q

OPERABLE status (ACTION a.1). Alternately, the inoperable channel, or

.i associated trip system, may be ) laced in trip (ACTION a.2), since this would conservatively compensate for tie inoperability, restore capability to acconmodate a single failure, and allow operation to continue. As noted, placing the channel in trip with no further restrictions is not allowed if the inoperable channel is the result of an inoperable condenser vacum pmp trip breaker or isolation valve, since this may not adequately conpensate for the j

I BRlNSWICK - LMIT 1 B 3/4 3 7

' Amendnent No.185 l

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' (i INST M NTATION fl BASES i'

3/4.3.8 CONDENSER VACUW PWP ISG.ATION INSTRtfENTATIM 8

ACTIM a.

(continued)

'10 inoperable condenser vacum pmp trip breaker or isolation valve (e.g.. the ij trip breaker may be inoperable such that it will not trip). If it is not desired to place the channel in trip (e.g., as in the case d ere placing the 2

inoperable channel would result in loss of condenser vacuum), or if the

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inoperable channel is the result of an inoperable condenser vacuum pump trip

! j breaker or isolation valve, the plant must be brought to an operati j

condition in dich the Limiting Condition for Operation does not as To i

achieve this status, the plant must be brought to at least OPERATIQ

,.I CONDITION 3 within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months . Alternately, the associated condenser vacuum pap (s) may be removed from service since this performs the intended function

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of the instraentation. An additional option is provided to isolate the main

'1 steam lines. d ich may allow operation to continue. Isolating the main steam 4i lines effectively provides an equivalent level of protection by precluding l

fission product transport to the condenser. This isolation is accoglished by j

isolation of all main steam lines and main steam line drains dich bypass the main steam isolation valves.

The allowed Completion Time of 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months is reasonable, based on operating experience, to reach OPERATIONAL CONDITION 3 from full )ower conditions, or to remove the condenser pump from service, or to isolate tie main steam lines in an orderly manner and without challenging plant systems.

ACTIM b.

ACTION b. is intended to ensure appropriate actions are taken if multiple.

1 inoperable, untripped channels result in the Function not maintaining condenser vacuum pug isolation capability. The Function is considered to be maintaining condenser vacuum p ap isolation capability when sufficient channels are OPERABLE or in trip such that the condenser vacum ) ump isolation Instruments will generate a trip signal from a valid Main Steam.ine Radiation High signal, and the condenser vacuum pumps will trip. This requires one channel of the function in each trip system to be OPERABLE or in trip and the condenser vacuum pump trip breakers to be OPERABLE. With condenser vacuum p ep isolation capability not maintained, the unit must be i

brought to an operati condition in which the Limiting Condition for I

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Operation does not app, Therefore, to achieve this, the unit must be placed in OPERATIONAL CONDITI 3 within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months (ACTION b.3). Alternatively, the 4

I condenser vacuum pep can be removed from service since this performs the intended function of the instrumentation (ACTION b.1). An additional option is provided to isolate the main steam lines (ACTION b.2).

Isolation of the main steam lines effectively provides an equivalent level of protection by precluding fission product transport to the condenser. This isolation is accomplished by isolation of all main steam lines and main steam line drains which bypass the main steam isolation valves.

An allowed completion time of 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months is reasonable, based on operating experience, to reach OPERATIONAL CONDITION 3 from full

)ower conditions, or to remove the condenser pump from service. or to isolate tie main steam lines, in an orderly manner and without challenging plant systems.

BRUNSWICK - UNIT 1 B 3/4 3 8 Amendnent No.185 l r

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E TF MENTATION

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BASES 1

3l 3/4.3.8 CONDENSER VACUUM PUMP ISOLATION INSTRUMENTATION (continued) bf u

ACTION c.

t dk ACTION c. allows that when a channel is placed in an inoperable status solely for performance of required Surveillances, entry into the associated Actions may be delayed for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months provided the associated Function maintains i{.

condenser vacuum pump isolation trip capability. Upon com)letion of the 6; t Surveillance or ex)1 ration of the 6 hour6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months allowance, the ciannel must be

i returned to OPERABLE status or the applicable Condition entered and Required Actions taken. This Note is based on the reliability analysis (Ref. 1) assumption of the average time required to perform channel Surveillance. That d

analysis demonstrated that the 6 hour6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months testing allowance does not significantly reduce the probability that the condenser vacuum pumps will isolate when necessary.

q Surveillance Reauirement 4.3.8.a j ':

Performance of the CHANNEL CHECK once every 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ensures that a gross failure of instrumentation has not occurred. A CHANNEL CHECK will detect gross channel failure: thus it is key to verifying the instrumentation continues to operate properly between each CHANNEL CALIBRATION.

Surveillance Reauirement 4.3.8.b A CHANNEL FUNCTIONAL TEST is performed to ensure that the entire channel will L i

.3 perfom the intended function. Any setpoint adjustment shall be consistent with the assumptions of the current plant specific setpoint methodology.

The 92 day frequency is based on the reliability analysis of Reference 1.

Surveillance Reauirement 4.3.8.c

.l A CHANNEL CALIBRATION is a complete check of the instrument loop and the 7

sensor. This test verifies the channel res>onds to the measured parameter within the necessary range and accuracy. CiANNEL CALIBRATION leaves the 4

i 4 channel adjusted to account for instrument drifts between successive calibrations consistent with the plant specific setpoint methodology. The 18 month frequency is conservative with respect to the assumption of the calibration interval in the determination of the magnitude of equipment drift i

in the setpoint analysis.

4 For the purposes of this surveillance, background is the dose level experienced at 100% rated thermal power with hydrogen water chemistry at the maximum injection rate. Under these conditions, an Allowable Value of 6 x 4

background will ensure that General Design Criterion 19 limits will not be exceeded in the control room in the event of a control rod drop accident.

BRUNSWICK - UNIT 1 8 3/4 3-9 Amendment No.185 l

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INSTRLNENTATION BASES 3/4.3.8 CONDENSER VACulN PLMP ISOLATION INSTRlNENTATION (continued)

Surveillance Reauirement 4.3.8.d 1

i The LOGIC SYSTEM FUNCTIONAL TEST demonstrates the OPERABILITY of the required tri logic for a specific channel. The system functional test of the ptmp tri breakers and actuation of the associated isolation valve are included as part of this Surveillance and overlaps the LOGIC SYSTEM FUNCTIONAL TEST to j

provide complete testing of the asstned safety function. Therefore, if a breaker 1s incapable of operating or isolation valves incapable of actuating, the instrument channel would be inoperable.

The 18 month frequency is based on the need to perform this Surveillance under the conditions that app during a plant outage and the potential for an 3

unplanned transient if e surveillance were performed with the reactor at-1 power.

Reference 1.

NEDC-30851P-A Supplement 2. Technical Specifications Improvement i

Analysis for BWR Isolation Instrumentation Comon to RPS and ECCS Instrumentation, March 1989.

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i BRUNSWICK - UNIT 1 B 3/4 3 10 Amendment No.185 l

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UNITED STATES p

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NUCLEAR REGULATORY COMMISSION r

f WASHINGTON. D.C. 30006 4001 i

+s...../

CAROLINA POWER & LIGHT COMPANY. et al.

DOCKET NO. 50-324 BRUNSWICK STEAM ELECTRIC PLANT. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE 3

Amendment No. 216 License No. DPR-62 1.

The Nuclear Regulat' ory Comission (the Comission) has found that:

)

A.

The application for amendment filed by Carolina Power & Light Company (the licensee), dated March 5, 1997, as supplemented May 9, 1997, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) 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 (1) that the activities authorized i

by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be 4

conducted in compliance with the Comission's regulations-J 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; i

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.

t 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 Soecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 216, are hereby incorporated in the license. Carolina Power & Light Company shall operate the facility in accordance with the Technical Specifications.

3.

This license amendt.. ant is effective as of the date of its issuance and shall be implemented prior to the next reactor startup requiring operation of the condenser vacuum pump, but no later than the end of refueling outage 12 (B213RI).

FOR THE NUCLEAR REGULATORY COMMISSION Qw

/

g g.1fff?lW90 Mark Re

art,

'ing Director Project Direc orate 11-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: May 9, 1997 e

ATTACHMENT TO LICENSE AMENDMENT NO. 216 FACILITY OPERATING LICENSE NO. DPR-62 DOCKET NO. 50-324 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised areas are indicated by marginal lines.

Remove Paaes Insert Paaes V

V X

X 3/4 3-104 3/4 3-105 B3/4 3-7 B3/4 3-7 B3/4 3-8 B3/4 3-9 83/4 3-10 B3/4 3-11 4

O INDEX 1

LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION EME

'I 3/4.3 INSTRlNENTATION 3/4.3.1 REACTOR PROTECTION SYSTEM INSTRlMENTATION.................

3/4 3-1 4

3/4.3.2 ISOLATION ACTUATION INSTRlMENTATION.......................

3/4 3-10 3/4.3.3 EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRLMENTATION... 3/4 3-33 i

3/4.3.4 CONTROL R00 WITHDRAWAL BLOCK INSTRUMENTATION..............

3/4 3-47 j

3/4.3.5 MONITORING INSTRUMENTATION Seismic Monitoring Instrumentation........................

3/4 3-53 Remote Shutdown Monitoring Instrumentation................

3/4 3-56 Accident Monitoring Instrumentation.......................

3/4 3-59 i

Source Range Monitors.....................................

3/4 3 63 Control Room Emergency Ventilation System.................

3/4 3-64 Chloride Intrusion Monitors.............................. 3/4 3-65 j

Fire Detection Instrumentation (Deleted)..................

3/4 3 69 Radioactive Liquid Effluent Monitoring Instrumentation.... 3/4 3-72 Radioactive Gaseous Effluent Monitoring Instrumentation... 3/4 3-78 3/4.3.6 RECIRCULATION PlMP TRIP ACTUATION INSTRlMENTATION ATWS Recirculation Ptap Trip (RPT) System Instrumentation. 3/4 3-88 End-of-Cycle Recirculation Ptap Trip System Instrumentation........................................

3/4 3-93 hRUM Tkb 3/4 3 99 3/4.3.8 CONDENSER VACUlM PUMP ISOLATION INSTRUMENTATION........... 3/4 3 104 l I

1 3/4.4 REACTOR COOLANT SYSTEM j

3/4.4.1 RECIRCULATION SYSTEM Recirculation Loops.......................................

3/4 4-1

<l Jet Pumps......................................

.......... 3/4 4-2 i

j Idle Recirculation Loop Start-up..........................

3/4 4-3 3/4.4.2 SAFETY / RELIEF VALVES.................................... 3/4 4-4 3/4.4.3 REACTOR COOLANT SYSTEM LEAKAGE Leakage Detection Systems...............

................. 3/4 4-5 Operational Leakage.................................... 3/4 4-6 l

1 BRUNSWICK UNIT 2 V

Amendment No. 216 i

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ji INDEX

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BASES 4.l.

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SECTION E8GE 1a

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3/4.0 ' APPLICABILITY..............................................

B 3/4 0-1 3/4.1 REACTIVITY CONTROL SYSTEMS Nq l

3/4.1.1 SHUTDOWN MARGIN..........................................

B 3/4 1-1 1

3/4.1.2 REACTIVITY AN0MALIES.....................................

B 3/4 1-1 F

3/4.1.3 CONTROL R0DS.............................................

B 3/4 1-1 3/4.1.4 CONTROL-R00 PROGRAM CONTR0LS.............................

B 3/4 1-3 3/4.1.5 STANDBY LIQUID CONTROL SYSTEM...........................,

B 3/4 1-4

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3/4.2 POWER DISTRIBlfTION LIMITS 1

3/4.2.1 AVERAGE PLANAR LINEAR HEAT GENERATION RATE...............

B 3/4 2-1 3/4.2.2 MINIMUM CRITICAL POWER RATI0.............................

B 3/4 2-2 3/4.3 INSTRUMENTATION

~3/4.3.1 REACTOR PROTECTION SYSTEM INSTRUMENTATION................

B 3/4 3-1 3/4.3.2 ISOLATION ACTUATION INSTRUMENTATION......................

B 3/4 3-2 3/4.3.3 EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION..B 3/4 3-2 3/4.3.4 CONTROL R0D WITmRAWAL BLOCK INSTRtNENTATION.............

B3/4 3-2a 3/4.3.5 MONITORING INSTRUMENTATION...............................

B3/4 3-2a l

3/4.3.6 RECIRCULATION PtNP TRIP SYSTEM INSTRUMENTATION...........

B 3/4 3-6 hRlN Tk B 3/4 3-7 l

3/4.3.8 CONDENSER VACVUM PUMP ISOLATION INSTRUMENTATION..........

B 3/4 3-7 1 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 RECIRCULATION SYSTEM....................................

B 3/4 4-1 3/4.4.2 SAFETY / RELIEF VALVES.....................................

B 3/4 4-1

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3/4.4.3 REACTOR COOLANT SYSTEM LEAKAGE...........................

B 3/4 4-1 l

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i BRUNSWICK - UNIT 2; X

Amendnent No. 216 l.

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i INSTRtNENTATION f

3/4 3.8 CONDENSER VACUUM PlNP ISOLATION INSTRtNENTATION J

LIMITING CONDITION FOR OPERATION a

I 1d 3.3.8 Four channels of the Main Steam Line Radiation-High Function for the condenservacuumgerequiredAllowableValue. ump isolation shall be OPERABLE with consistent with t J

1 APP'LICABILITY:

OPERATIONAL CONDITIONS 1 and 2 with a condenser vacuum pump in service.

t ACTION-a.

With one or more channel (s) of the Main Steam Line Radiation-High l

Function for condenser vacuum puno isolation inoperable:

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1.

Restore channel to OPERABLE status within 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months s: or

2.

Place channel or associated trip system in trip within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

y Otherwise;isolatethecondenservacuump)sorisolatethemainsteam lines, or be in HOT SHUTDOWN within the ne 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

b.

With condenser vacuum pump isolation capability not maintained:

1.

Isolate the condenser vacuum pumps within 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months s: or 2.

Isolate the main steam lines within 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months s: or 3.

Be in HOT SHlffDOWN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

c. When a channel is placed in an inoperable status solely for the performance of required Surveillances, entry into associated Actions may be delayed for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months provided condenser vacuum pump isolation capability is maintained.

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Not applicable if the inoperable channel is the result of an inoperable condenser vacuum pump trip breaker or isolation valve.

BRUNSWICK - UNIT 2 3/4 3-104 Amendment No. 216 l

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j l INSTRtMENTATION

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3/4.3.8 CONDENSER VACulM PtMP ISOLATION INSTRIMENTATION SURVEILLANCE REQUIREMENTS 4.3.8 Each channel of the Main Steam Line Radiation-H_igh Function for gj condenser vacuum pump isolation shall be demonstrated OPERABLE by:

a.

Performance of a CHANNEL CHECK at least once per-24 hours:

i b.

Performance of a CHANNEL FUNCTIONAL TEST at least once per 92 days:

c.

Performance of a CHANNEL CALIBRATION at least once per 18 months.

j the Allowable Value shall be s 6 x background: and d.

Performance of a LOGIC SYSTEM FUNCTIONAL TEST. including condenser vacuum pump tri breaker and isolation valve actuation at least once per 18 mon hs.

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BRUNSWICK - UNIT 2 3/4 3-105 Amendnent No. 216 l

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INSTRUMENTATION BASES 3/4:3.7 REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION INSTRUMENTATIO The reactor core isolation cooling system actuation instrumentation is provided to initiate actions to assure adequate core cooling in the event of reactor isolation from its primary heat sink and the loss of feedwater flow to the reactor vessel without providing actuation of any of the emergency core cooling equipment.

Specified surveillance intervals and allowed out-of-service times were established based on the reliability analyses documented in GE report GENE-770-06-2P-A. " Bases for Changes to Surveillance Test Intervals and Allowed Out-of-Service Times for Selected Instrumentation Technical Specifications." December 1992.

3/4.3.8 CIMENSER VArtillM PLMP IS1ATI(W INSTRLDENTATION Backaround The condenser vacuum pump isolation instrumentation initiates a trio of the respective condenser vacuum pump and the connon isolation valve following events in which the main steam line radiation monitor (s) exceed a predetermined value.

The condenser vacuum pump 1solat initiates an isolation of the condenser vacuum pump (s) ion instrumentationto limit main contro room doses resultino frun fuel cladding failure in the event of a control rod drop accident (CRDA).

i The isolation logic consists of two indeoendent trip systems with two channels of the Main Steam Line Radiation-High Function in eachtripsystem.

1 Each trip system is a one-out-of-two logic for this Function.

in each trip sys, tem are needed to trio a trio system.Thus either channel of the The outputs of the channels are arranged in a logic so that both trip systems must trip to result in an isolation signal.

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e BRUNSWICK - UNIT 2 B 3/4 3-7 Amendment No. 216

INSTRLNENTATION BASES 3/4.3.8 CONDENSER VACUUM PlNP ISOLATION INSTRUMENTATION (continued)

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O The OPERABILITY of the condenser vacuum pump isolation is dependent on the

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OPERABILITY of the individual Main Steam Line Radiation High Function instrument channels dich must have its setpoint within the specified AllowableValueof$urveillanceRequirement4.3.8.c. The actual setpoint is calibrated consistent with applicable setpoint methodology asstaptions.

Channel 0PERABILITY also includes the condenser vacuum pump trip breaker and 1 solation valve.

Acolicability The condenser vacuum pump isolation is required to be OPERABLE in OPERATIONAL CONDITIONS 1 and 2 when a condenser vacuum pump is in service. to mitigate the I

consequences of a postulated control rod drop accident.. In this condition,

! i fission products released during a control rod drop accident could be discharged directly to the environment. Therefore, the condenser vacum pump 1 solation is necessary to assure conformance with the radioloalcal evaluation of the control rod drop accident.

In OPERATIONAL CONDITIONS 3. 4. or 5. the consequences of a control rod drop are insignificant and are not expected to result in any fuel damage or fission product releases. When a condenser vacuum pump 1s not in operation in OPERATIONAL CONDITIONS 1 or 2, fission product releases via this pathway would not occur.

ACTION a.

With one or more channels inoperable but with condenser vacuum pump isolation

)

capability maintained (refer to ACTIdN b. Bases), the condenser vacuum pep isolation instrumentation is capable of performing the intended function.

However, the reliability and redundancy of the condenser vacuum Dump isolation instrumentation is reduced, such that a single failure in one of' the remaining

^

channels could result in the inability of the condenser vacuum pump isolation instrumentation to perform the intended function. Therefore, only a limited time is allowed to restore the inoperable channels to OPERABLE status.

Because of the low probability of extensive numbers of inoperabilities 4

affecting multiple channels, and the low probability of an event requiring the j

initiation 'of condenser vacuum pump isolation,12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months has been shown to be acceptable (Ref. 1) to permit restoration of any inoperable channel to OPERABLE status (ACTION a.1). Alternately, the inooerable channel, or associated trip system. may be placed in trip (ACTION a.2), since this would conservatively compensate for the inoperability, restore capability to accommodate a single failure, and allow operation to continue. As noted placingthechannelintripwithnofurtherrestrictionsisnotallowedif.the inoperable channel is the result of an inoperable condenser vacuum p ap trip breaker or isolation valve. since this may not adequately compensate for the l

LBRUNSWICK - UNIT 2 B 3/4 3 8 Amendment No. 216 j 1

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I INSTRUMENTATION j

BASES 3/4.3.8 CONDENSER VACUUM PUMP ISOLATION INSTRLMENTATION ACTION a.

(continued) in rable condenser vacuum o mp trip breaker or isolation valve (e.g., the tri breaker may be inoperable such that it will not trip).

If it is not des red to place the channel in trio (e.g., as in the case where placing the inoperable channel would result in I m of condenser vacuum), or if the j

inoperable channel is the result of an inoperable condenser vacu m p ap trip breaker or isolation valve, the Diant must be brought to an operatin I

condition in W11ch the Limitir.g Condition for Operation does not a To I

achieve this status the p u nt must be brought to at least OPERATI CONDITION 3within12 hows. Alternately, the associated condenser vacuum pump (s) may be removed iram service since this performs the intended function of the instreentation. An additional option is provided to isolate the main steam lines, whic% may allow operation to continue.

Isolating the main steam

.i lines effectively provides an equivalent level of protection Dy precluding fission product transport to the condenser. This 1 solation is accomplished by isolation of all main steam lines and main steam line drains which bypass the main steam isolation valves.

The allowed Completion Time of 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months is reasonable based on operating experience,toreachOPERATIONALCONDITION3fromfulloowerconditions,orto remove the condenser pump from service or to isolate the main steam lines, in an orderly manner and without challengi,ng plant systems.

ACTION b.

ACTION b. is intended to ensure appropriate actions are taken if multiple, inoperable, untripped channels result in the Function not maintaining condenser vacuum pump 1 solation capability. The Function is considered to be maintaining condenser vacuum pump 1 solation capability When sufficient channels are OPERABLE or in trip such that the condenser vacuum cump isolation instruments will generate a trip signal from a valid Main Steam Line and the condenser vacuum pumps will trip. This Radiation-High signal,f the function in each trip system to be OPERABLE or in requires one channel o tr1p and the condenser vacuum pumn trip breakers to be OPERABLE. With condenser vacuum pump isolation capabiiity not maintained, the unit must be brought to 'an operatin condition in which the Limiting Condition for 3within12, hours (ACTIONb.8)theunitmustbeplaced Therefore to achieve this Operation does not apo Alternatively, the in OPERATIONAL CONDITI s) can be removed from service since this performs the condenser vacuum pump (he instrumentation (ACTION b.1).

intended function of t An additional ootion is provided to isolate the main steart lines (ACTION b.2).

Isolation of'the main steam lines effectively provides an equivalent level of protection by precluding fission product transport to the condenser. This isolation is accomplished by isolation of all main steam lines and main steam line drains which bypass the main steam isolation valves.

An allowed completion time of 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months is reasonable based on operating experience,toreachOPERATIONALCONDITION3fromfullDowerconditions,orto remove the condenser pump from service or to isolate the main steam lines, in an orderly manner and without challeng,ng plant systems.

i BRUNSWICK UNIT 2 B 3/4 3-9 Amendment No. 216. l

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INSTR 1M NTATION q

I 3,

BASES

i-3/4.3.8 CO MENSER VAd (co & nued)

ACTI(N c.

e' ACTIONc.allowsthatWnachanN1ances.-entryintotheassociatedActions1 is placed "IdJ for oerformance of required Surve ia may be delayed for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months provided the associated Function maintains I

condenser vacuum pump isolation trip capability. Upon coeletion of the a

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Surveillance or ex}1 ration of the 5 hour5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months allowar.cs, the channel must be returnedtodPERABL:statusortheapplicableCanditionenteredandReq)uired i

Actions taken. This Note is based on the reliability analysis (Ref. 1 L. 1 4

ass tion of the averaoe time requirec to perform channel Surveillance. That ana is demnstrated tfiat the 6 hour6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months testing allowance does not significantly r

e the probability that the condenser vacuta pumps will isolate when j-necessary.

1; I' Surveillance Reauirmont 4.3.8.a i

PerformnceoftheCHANNELCHECKonceeveh.24hoursensuresthaACHAN a ross failure of instrumentation has not occurr 1

continues to operate properly between each CHAMing the instrtmentation gross channel failure: thus it is key to verif i

EL CALIBRATION.

f Surveillance Reauirement 4.3.8.b A CHANNEL FlMCTIONAL TEST is performed to ensure that the entire channel will perform the intended function. Any setpoint adjustment shall be consistent with the assumptions of the current plant specific setpoint methodology.

pi The 92 day frequency is based on the reliability analysis of Reference 1.

l Surveillance Reauirment 4.3.8.c

[

ACHANNELCALIBRATIONisac$channelrespondstothemeasukparameter lete check of the instrument 1 and the sensor. This test verifies t within the necessary range and accuracy. CHANNEL CALIBRATION leaves the 4

channel adjusted to account for instrument drifts between successive calibrations consistent with the plant specific setpoint methodology. The 18 month frequency is conservative with respect to the assumption of the 4

calibration interval in the determination of the magnitude of equipment drift in the setpoint analysis.

For the purposes of this surveillance, background is the dose level experienced at 100% rated thermal power with hydrogen water chemistry at the maximum injection rate. Under these conditions, an Allowable Value of 6 x background will ensure that General Design Criterion 19 limits will not be-

.jl exceeded in the control room in the event of a control rod drop accident.

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BRUNSWICK - UNIT 2.

B 3/4 3-10 Amendment No. 216 l

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3STRLNENTATION f

BASES 3/4.3.8 CONDENSER VACUUM PUMP ISOLATION INSTRlNENTATION (continued)

Surveillance Reauirement 4.3.8.d J

J The LOGIC SYSTEM FUNCTIONAL TEST demonstrates the OPERABILITY of the required d

tri logic for a specific channel. The system functional test of the pump tri breakers and actuation of the associated isolation valve are included as par of this Surveillance and overlaps the LOGIC SYSTEM FUNCTIONAL TEST tc

,j provide complete testing of the assumed safety function. Therefore, if a breaker is incapable of operating or isolation valves incapable of actuating,

!, J the instrument channel would be inoperable.

The 18 month frequency is based on the need to perform this Surveillance under 4

the conditions that apolv during a plant outage and the potential for an unplanned transient if the surveillance were performed with the reactor at power.

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Reference Technical Specifications Imorovement NEDC-30851P-A Supplement 2, Instrumentation Coninon to RPS and ECCS 1.

Analysis for BWR Isolation Instrumentation March 1989.

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BRUNSWICK - UNIT 2 B 3/4 3-11 Amendnent No. 216 l r

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