Text

Amends 193 & 197 to Licenses DPR-44 & DPR-56,respectively, Re Changes to TS to Modify Existing Lco,Srs & Bases to Reflect New Containment Monitoring Sys Analyzers
	ML20072C414
Person / Time
Site:	Peach Bottom
Issue date:	08/10/1994
From:	Thadani M; Office of Nuclear Reactor Regulation
To:	;
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ML20072C417	List: ML20072C414;
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	NUDOCS 9408170229
	Download: ML20072C414 (18)
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4 UNITED STATES p

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NUCLEAR REGULATORY COMMISSION 2

WASHINGTON. D.C. 206 6 0001

'+9.....,o PHILADELPHIA ELECTRIC COMPANY PUBLIC SERVICE ELECTRIC AND GAS COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-277 PEACH BOTTOM ATOMIC POWER STATION. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 193 License No. DPR-44 1.

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

A.

The application for amendment by Philadelphia Electric Company, et al. (the licensee) dated April 27, 1994, 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 (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 or 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 4

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-44 is hereby amended to read as follows:

9408170229 940810 PDR ADOCK 05000277 P

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.- (2) Technical Specification 1 The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 193, are hereby incorporated in the license.

PECO shall operate the facility in accordance with the Technical Specifications.

3.

ThislicenseamendmentiseffectivepriortothestartupofUnit2 following refueling outage 2R10.

FOR THE NUCLEAR REGULATORY COMMISSION bb C.

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~ Mohan C. Thadani, Acting irector Project Directorate I-2 Division of Reactor Projects - 1/Il Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance:

August 10, 1994 l

a 4

ATTACHMENT TO LICENSE AMENDMENT NO.193 FACILITY OPERATING LICENSE NO. DPR-44 DOCKET NO. 50-277 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised areas are indicated by marginal lines.

Remove Insert 77a 77a 78a 78a 86a 86a 93 93 172 172 173 173 194 194 e

TABLE 3.2.F (Cont'd) - SURVEILLANCE INSTRUMENTATION Minimum No.

of Operable Type Instrument Indication Itea Channels Parameter Instrument and Range Action

11 2

Suppression Chamber LR-8(9)123A, B Recorder 1-21 ft.

(10) (11)

Water Level (wide range) 12 1

Control Rod Position N/A 28 Volt Indicating )

Lights

)

(1) (2) (3) (4)

)

13 1

Neutron Monitoring N/A SRM, IRM, LPRM,

)

0-100%

)

14 1

Safety-Relief Valve P0AM-2(3)-2-71A-L Acoustic or (5)

Position Indication TE-2(3)-2-113A-L Thermoccuple 15 2

Drywell High RR-8(9)l03A, B Recorder Range Radiation 1-lE(+8) R/hr (7)

Monitors d 16 1

Main Stack High Range RR-0-17-051 Regorder 11 i

Radiation Monitor 10 to 10 CPS (7)

(Log Scale) 17 1

Reactor Building Roof RR-2979 (Unit 2)

Regorder 13 Vent High Range Radiation RR-3979 (Unit 3) 10 to 10 CPM (7)

Monitor (Log Scale) 18 2

Drywell Hydrogen 2(3)AC872, 2(3)BC872 Analyzer and Recorder (13)

Concentration Analyzer XR-8(9)0411A, 0-30% volume and Monitor XR-8(9)0411B 19 2

Suppression Chamber 2(3)AC872,2(3)BC872 Analyzer and Recorder (13)

Hydrogen Concentration XR-8(9)0411A, 0-30% volume Analyzer and Monitor XR-8(9)D411B

Notes for Table 3.2.F appear on pages 78 and 78a.

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Amendment No. 113, 128. 189, 193

PBAPS Unit 2 NOTES FOR TABLE 3.2.F (Cont'd) 9)

If no channels are operable, continued operation is permissible during the succeeding 7 days, provided both Drywell Pressure instruments (0-70 psig) are operable; otherwise, restore the inoperable channel (s) to operable status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 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 .

10)

With the number of operable channels less than the minimum number of instrumentation channels shown in Table 3.2.F, continued operation is permissible during the succeeding 30 days, provided both narrow range instruments monitoring the same variable are operable; otherwise, restore the inoperable channel 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 .

11)

If no channels are operable, continued operation is permissible during the succeeding seven days, provided both narrow range instruments monitoring the same variable are operable; otherwise, restore the inoperable channel (s) to operable status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 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 .

12)

The instrument range may be greater than the range listed in Table 3.2.F provided that (1) the range includes the upprir and lower range limits specified in Table 3.2.F, and (2) the range does not exceed three times the range specified in Table 3.2.F.

13)

With only 1 channel operable to monitor hydrogen concentration, restore the inoperable channel to operable status within 30 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 .

With no channels operable to monitor hydrogen concentration, restore an inoperable channel 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 .

-78a-Amendment No. 113, 128. 193

TABLE 4.2.F MINIMUM TEST AND CALIBRATION FREQUENCY FOR SURVEILLANCE INSTRUMENTATION Instrument Channel Calibration Frequency Instrument Check 18)

Drywell High Range Radiation Monitors Once/ operating cycle **

Once/ month 19)

Main Stack High Range Once/ eighteen months Once/ month Radiation Monitor 20)

Reactor-Bldg. Roof Vent Once/ eighteen months Once/ month High Range Radiation Monitor 21)

Drywell and Suppression Chamber Hydrogen Quarterly ***

Once/ month Concentration Analyzer and Monitor a

Perform instrument functional check once per operating cycle.

?

Channel calibration shall consist of an electronic calibration of the channel, not including the detector, for range decades above 10R/hr i

and a one point calibration check of the detector below 10R/hr with an installed or portable gamma source.

At least a two-point calibration using sample gas.

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Unit.2 PBAPS 3.2 BASES (Cont'd)

Four sets of two radiation monitors are provided which initiate the Reactor Building Isolation function and operation of the standby gas treatment system.

Four instrument channels monitor the radiation from the refueling area ventilation exhaust ducts and four instrument channels monitor the building ventilation below the refueling floor.

Each set of instrument channels is arranged in a 1 out of 2 twice trip logic.

Trip settings of less than 16 mr/hr for the monitors in the refueling area ventilation exhaust ducts are based upon ini-tiating normal ventilation isolation and standby gas treatment system operation so that none of the activity released during the refueling accident leaves the Reactor Building via the normal ventilation path but rather all the activity is processed by the standby gas treatment system.

Two channels of nonsafety-related radiation monitors are provided in the main stack.

Trip signals from these monitors are required only when purging the containment through the SGTS and containment integrity is required.

The trip signals isolate pri-mary containment vent and purge valves greater than 2 inches in diameter to prevent accidental releases of radioactivity offsite when the valves are open.

This signal is added to fulfill the requirements of item II.E.4.2(7) of NUREG-0737.

Four channels of in-duct radiation monitors are provided which initiate the Main Control Room Emergency Ventilation System.

Each set of instrument channels are arranged in a one (1) out of two (2) twice trip logic.

Flow integrators are used to record the integrated flow of liquid from the drywell sumps.

The integrated flow is indica-tive of reactor coolant leakage.

A Drywell Atmosphere Radioactivity Monitor is provided to give supporting information to that supplied by the reactor coolant leakage monitoring system.

(See Bases for

3. 6. C and 4. 6.C)

Some of the surveillance instrumentation listed in Table 3.2.F are required to meet the accident monitoring requirements of NUREG-0737, Clarification of TMI Action Plan Requirements.

This instrumentation and the applicable NUREG-0737 requirements are:

1.

Wide range drywell pressure (II.F.1.4) 2.

Subatmospheric drywell pressure (II.F.1.4) 3.

Wide range suppression chamber water level (II.F.1.5) 4.

Main stack high range radiation monitor (II.F.1.1) 5.

Reactor building roof vent high range radiation monitor (II.F.1.1) 6.

Drywell hydrogen concentration analyzer and monitor (II.F.1.6) 7.

Drywell high range radiation monitors (II.F.1.3) 8.

Reactor Water Level - wide and fuel range (II.F.2) 9.

Safety-Relief Valve position indication (II.D.3)

The suppression chamber hydrogen concentration analyzer and monitor are listed as an enhancement made by Mod 5274 (see 3.7.A Bases for a discussion of the CAD hydrogen and oxygen analyzers). Amendment No. 102, 112, 113.

156, Z84, 193

Unit 2 PBAPS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE RE0VIREMENTS 3.7.A Primary Containment 4.7.A Primary Containment 6.

Containment Atmosohere Dilution 6.

Containment Atmosohere a.

Whenever either reactor is in Dilution power operation, the Post-LOCA Containment Atmosphere Dilution a.

The post-LOCA containment System must be operable and atmosphere dilution capable of supplying nitrogen system shall be to either Unit 2 or Unit 3 functionally tested once containment for atmosphere per operating cycle.

dilution if required by post-LOCA conditions.

If this specification cannot be met, b.

The level in the liquid the system must be restored to nitrogen storage tank an operable condition within 30 shall be verified in days or both reactors must be accordance with taken out of power operation.

Specification 4.7.E.3.a.

b.

Whenever either reactor is in power operation, the post-LOCA Containment Atmosphere Dilution System shall contain a minimum of 2500 gallons of liquid nitrogen.

If this specification cannot be met, the minimum volume will be restored within 30 days or both reactors must be taken out of power operation.

c.

Whenever the reactor is in power operation, there shall be 2 analyzers operable to monitor oxygen concentration in the containment atmosphera.

There shall be 2 channel:, operable to monitor drywell oxygen concentration and 2 channels operable to monitor torus oxygen concentration.

With only 1 channel operable to monitor drywell oxygen concentration or with only 1 channel operable to monitor torus oxygen concentration, restore the inoperable channel (s) 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 .

-172-Amendment No. 58, 113, I63, 177, 193

Unit 2 PBAPS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE RE0VIREMENTS 3.7.A.6.c (Cont'd) 4.7.A.6 (Cont'd)

With no channels c.

The analyzers shall be operable to monitor tested for channel ch.eck drywell oxygen once per month and shall concentration or no have channel calibration channels operable to using bottled gas once monitor torus oxygen per 3 months. The concentration, restore atmospheric analyzing the inoperable system shall be channel (s) to operable functionally tested once status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months per operating cycle in or be in at least Hot conjunction with the Shutdown within the next specification 4.7.A.6.a.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

d.

Technical Specification requirements for hydrogen are detailed separately in Table 3.2.F/4.2.F.

e.

A 30 psig limit is the l

maximum containment repressurization allowable using the CAD system.

Venting via the SBGT system to this stack must be initiated at 30 psig following the i

initial peak pressure at 49.1 psig.

l l

-173-Amendment No. 24 69, 77, II2, 195

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l Unit 2 PBAPS 3.7.A & 4.7.A ESEE (Cont'd) periodictestingoff.hesystemisrequired. Twice weekly operation of

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the containment oxygen analyzer that is associated with the containment inerting makeup system is sufficient to insure its readiness. Reliance on that oxygen analyzer for this purpose of post-LOCA oxygen measurement will terminate when the CAD system is operable.

The Post-LOCA Containment Atmosphere Dilution system design basis and description are presented in Question 14.6 of.the FSAR.

In summary, the limiting criteria, based on the assumptions of Safety Guide 7, are:

1.

Maintain oxygen concentration in the containment during i

post-LOCA conditions to'less than 5% Volume.

2.

Limit the buildup in the containment pressure due to nitrogen addition to less than 30 psig.

3.

To limit the offsite dose due to containment venting (for pressure control) to less than 30 Rem to the thyroid.

By maintaining at least a 7-day supply of nitrogen on site, there will-be sufficient time after the occurrence of a LOCA for obtaining j

additional nitrogen supply from local commercial sources which have been discussed in Question 14.6 of the FSAR. The system design contains i

sufficient redundancy to ensure its reliability. Thus, it is sufficient to test the operability of the whole system once per operating cycle.

Drywell and suppression chamber hydrogen and oxygen analyzers are provided to detect high hydrogen or oxygen concentration conditions. The drywell and suppression chamber hydrogen and oxygen analyzer instrumentation consists of i

two independent gas analyzers.

Each gas analyzer can determine hydrogen and oxygen concentration. The analyzers are capable of determining hydrogen l

concentration in the range of 0 to 305 by volume and oxygen concentration in the range of 0 to 10% by volume.

Each gas analyzer must be capable of sampling either the drywell or the suppression chamber. The hydrogen and-oxygen concentration from each analyzer are displayed on its associated L

control room recorder.

Each analyzer is also provided with two sample pumps.

L Only one pump is required for analyzer operation. The CAD analyzers are not normally in service. They are manually placed in service from the control l

room following a LOCA.

The Technical Specification requirements for hydrogen are detailed separately in Tables 3.2.F/4.2.F.

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-194-Amendment No. IZ3.193

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j NUCLEAR REGULATORY COMMISSION t

WASHINGTON. D.C. 2066 Moot n

PHILADELPHIA ELECTRIC COMPANY PUBLIC SERVICE ELECTRIC AND GAS COMPANY l

DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY I

DOCKET NO. 50-278 PEACH BOTTOM ATOMIC POWER STATION. UNIT NO. 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 197 License No. DPR-56 1.

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

A.

The application for amendment by Philadelphia Electric Company, et al. (the licensee) dated April 27, 1994, complies with the standards l

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 l

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 and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; j

D.

The issuance of this amendment will not be inimical to the common defense and security or.to the health or 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-55 is hereby amended to read as follows:

t.

(2) Technical Soecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 197, are hereby incorporated in the license.

PEC0 shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective prior to the startup of Unit 2 following refueling outage 2R10.

FOR THE NUCLEAR REGULATORY COMMISSION b

0 Mohan C. Thadani, Acting Director Project Directorate I-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: August 10, 1994

1 ATTACHMENT TO LICENSE AMENDMENT NO.197 FACILITY OPERATING LICENSE N0. DPR-56 DOCKET NO. 50-278 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages.

The revised areas are indicated by marginal lines.

Remove Insert 77a 77a 78a 78a 86a 86a 93 93 194 194

TABLE 3.2.F (Cont'd) - SURVEILLANCE INSTRUMENTATION

~

Minimum No.

of Operable Type Instrument Indication Itea Channels Parameter Instrument and Range Action

11 2

Suppression Chamber LR-8(9)123A, B Recorder 1-21 ft.

(10) (11)

Water Level (wide range) 12 1

Control Rod Position N/A 28 Volt Indicating )

Lights

)

(1) (2) (3) (4)

)

13 1

Neutron Monitoring N/A SRM, IRM, LPRM,

)

0-100%

)

14 1

Safety-Relief Valve P0AM-2(3)-2-71A-L Acoustic or (5)

Position Indication TE-2(3)-2-ll3A-L Thermocouple 15 2

Drywell High RR-8(9)l03A, B Recorder Range Radiation 1-lE(+8) R/hr (7)

Monitors 4 16 1

Main Stack High Range RR-0-17-051 Regorder 11 Radiation Monitor 10 to 10 CPS (7)

(Log Scale) 17 1

Reactor Building Roof RR-2979 (Unit 2)

Regorder 13 Vent High Range Radiation RR-3979 (Unit 3) 10 to 10 CPM (7)

Monitor (Log Scale) 18 2

Drywell Hydrogen 2(3)AC872, 2(3)BC872 Analyzer and Recorder (13)

Concentration Analyzer XR-8(9)0411A, 0-30% volume and Monitor XR-8(9)04118 19 2

Suppression Chamber 2(3)AC872, 2(3)BC872 Analyzer and Recorder (13)

Hydrogen Concentration XR-8(9)D411A, 0-30% volume Analyzer and Monitor XR-8(9)04118

Nstes for Table 3.2.F appear on pages 78 and 78a.

Amendment No. II7, I3I, ISO, 194, 197

PBAPS Unit 3 NOTES FOR TABLE 3.2.F (Cont'd) 9)

If no channels are operable, continued operation is j

permissible during the succeeding 7 days, provided both Drywell Pressure instruments (0-70 psig) are operable; otherwise, restore the inoperable channel (s) to operable status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 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 .

10)

With the number of operable channels less than the minimum number of instrumentation channels shown in Table 3.2.F, continued operation is permissible during the succeeding 30 days, provided both narrow range instruments monitoring the same variable are operable; otherwise, restore the inoperable channel 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 .

11)

If no channels are ope'rable, continued operation is permissible during the succeeding seven days, provided both narrow range instruments monitoring the same variable are operable; otherwise, restore the inoperable channel (s) to operable status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 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 .

12)

The instrument range may be greater than the range listed in Table 3.2.F provided that (1) the range includes the upper and lower range limits specified in Table 3.2.F, and (2) the range does not exceed three times the range specified in Table 3.2.F.

13)

With only 1 channel operable to monitor hydrogen concentration, restore the inoperable channel to operable status within 30 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 .

With no channels operable to monitor hydrogen concentration, restore an inoperable channel 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 .

-78a-Amendment No. II7, 13I, 197

4 TABLE 4.2.F MINIMUM TEST AND CALIBRATION FREQUENCY FOR SURVEILLANCE INSTRUMENTATION Instrument Channel Calibration Frequency Instrument Check 18)

Drywell High Range Radiation Monitors Once/ operating cycle **

Once/ month 19)

Main Stack High Range Once/ eighteen months Once/ month Radiation Monitor 20)

Reactor Bldg. Roof Vent Once/ eighteen months once/ month High Range Radiation Monitor 21)

Drywell and Suppression Chamber Hydrogen Quarterly ***

Once/ month Concentration Analyzer and Monitor Perform instrument functional check once per operating cycle.

7 Channel calibration shall consist of an electronic calibration of the

. channel, not including the detector, for range decades above 10R/hr and a one point calibration check of the detector below 10R/hr with an installed or portable gamma source.

At least a two-point calibration using sample gas.

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Unit 3 PBAPS 3.2 BASES (Cont'd)

Four sets of two radiation monitors are provided which initiate the Reactor Building Isolation function and operation of the standby gas treatment system.

Four instrument channels monitor the radiation from the refueling area ventilation exhaust ducts and four instrument channels monitor the building ventilation below the refueling floor.

Each set of instrument channels is arranged in a 1 out of 2 twice trip logic.

Trip settings of less than 16 mr/hr for the monitors in the refueling area ventilation exhaust ducts are based upon ini-tiating normal ventilation isolation and standby gas treatment system operation so that none of the activity released during the i

refueling accident leaves the Reactor Building via the normal

)

ventilation path but rather all the activity is processed by the standby gas treatment system.