ML20212J299

Proposed Tech Specs Re Primary Coolant Sampling Analysis, Diesel Generator Surveillance & Auxiliary Electrical Sys. W/Certificate of Svc

ML20212J299
Person / Time
Site:	Peach Bottom
Issue date:	01/20/1987
From:	PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:
Shared Package
ML20212J254	List: ML20212J249 ML20212J278 ML20212J299
References
NUDOCS 8701280132
Download: ML20212J299 (8)

Text

PBAPS l.0 DEFINITIONS (Cont'd)

Simulated Automatic Actuation - Simulated automatic actuation means applying a simulated signal to the sensor to actuate the circuit in question.

Site Boundary - That line beyond which the land is not owned, leased or otherwise controlled by licensee.

Source Check - A source check shall be the qualitative assessment of channel response when the channel sensor is exposed to a radioactive source.

Startup/ Hot Standby Mode - In this mode the reactor protection scram trips, initiated by condenser low vacuum and main steam line isolation valve closure are bypassed, the reactor protection system is energized with IRM neutron monitoring system trip, the APRM 15% high flux trip, and control rod withdrawal interlocks in service.

This is often referred to as just Startup Mode.

This is intended to imply the Startup/ Hot Standby position of the mode switch.

Surveillance Frequency - Periodic surveillance tests, checks, calibrations, and examinations shall be performed within the specified surveillance intervals.

The operating cycle interval as pertaining to instrument and electrical surveillance shall not exceed 18 months.

These specified time intervals may be exceeded by 25%.

In cases where the elapsed interval has exceeded 100% of the specified interval, the next surveillance interval shall commence at the end of the original specified interval.

Surveillance tests are not required on systems or parts of the systems that are not required to be operable or are tripped.

If tests are missed on parts not required to be operable or are tripped, then they shall be performed prior to returning the system to an operable status.

A surveillance test of the diesel generators, that requires a plant outage, may be deferred beyond the calculated due date until the next refueling outage, provided the equipment has been similarly tested and meets the surveillance requirement for the other unit.

When a test is deferred under this provision, the next surveillance interval shall commence at the end of the original specified interval.

Transition Boiling - Transition boiling means the boiling regime between nucleate and film boiling.

Transition boiling is the regime in which both nucleate and film boiling occur intermittently with neither type being completely stable.

Trip System - A trip system means an arrangement of instrument channel trip signals and auxiliary equipment required to initiate i

l l j

8701280132 B70120 DR ADOCK 05000277 l

PDR t

PBAPS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS

'3.'.B Coolant Chemistry 4.6.B Coolant Chemistry 6

1.

Coolant Activity Limits 1.

During the equilibrium power operation the sampling Whenever the reactor is critical, frequencies of Table I shall the limits on activity concen-apply. Additional samples trations in the reactor coolant shall be taken whenever the i

chall not exceed the equili-reactor coolant concentration brium value of 0.2 uc/gm of exceeds ten percent of

. dose equivalent *I-131.-

the equilibium value in 3.6.B.1 and one or This limit may be exceeded for more of the following condi-a maximim of 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />. During tions are met:

this activity transient the

a. During startup i

iodine concentration shall not

b. Following a significant exceed the equilibrium value power change ***

of 4.0 uc/ gram of dose equiva-

c. Following a significant.

lent I-131 whenever the reactor increase ** in the is critical.

The reactor shall equilibrium offgas level not be operated under this ex-at the steam air ejector ception from the equilibrium over a 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period.

cctivity limits for more than 800 hours0.00926 days <br />0.222 hours <br />0.00132 weeks <br />3.044e-4 months <br /> in any consecutive Additional samples will also

)

12 month period.

If the iodine be obtained whenever the concentration in the coolant equilibrium iodine concen-exceeds 0.2 uc/ gram dose tration limit of 3.6.B.1 is squivalent I-131 for more than exceeded.

48 continuous hours or is greater than 4.0 uc/gm dose The additional coolant liquid squivalent I-131, the reactor samples shall be taken and shall be shutdown, and the analyzed isotopically for steam line isolation valves dose equivalent I-131

-shall be closed within at 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> intervals for 48 j

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

hours, or until two successive samples indicate a decreasing

• That concentration I-131 which trend below the limiting value alone would produce the same of 0.2 uc/gm dose equivalent thyroid dose as the quantity I-131.

However, at least and isotopic mixture actually 3 consecutive samples shall present.

be taken in all cases.

• • The following definition will apply to the term significant l

increase in offgas level.

a) At release rates less than or equal to 75,000 uc/sec, significant increase i

means an increase of 10,000 uc/sec from the previous corresponding power level steady state

]

release rate within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

• • • For the purpose of this b) At release rates greater section on sampling frequency than 75,000 uc/sec, signifi-a significant power change j

cant increase means an is defined as a change i

increase of 15% from the exceeding 15% of rated power previous corresponding in less than 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

power level steady state release rate within 1 hr.

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. ~. _ _ - _ _., _ _., _... -. _ _.,. _ _. _ _

PBAPS L[MITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.9'EAUXILIARY ELECTRICAL SYSTEM

'4.9 AUXILIARY ELECTRICAL SYSTEM Applicability:

Applicability:

Applies to the. auxiliary Applies to the periodic test-electrical power system.

ing requirements of the auxiliary electrical systems.

Objective:

Objective:

To assure an adequate supply Verify the operability of the of electrical power.for auxiliary electrica] system.

. operation of those systems required for safety.

Specification:

-Specification:

A.-

Auxiliary Electrical Equipment A. Auxiliary Electrical Equipment The reactor shall not be made-critical unless all of the following conditions are satisifed:

1.

Both'off-site sources,

1. Diesel Generators both 13.KV startup sources and er.ergency transformers are availhble and capable

a. Each diesel generator of~ automatically supplying shall be manually started power to the 4kV emergency and loaded once each buses.

month to demonstrate opera-tional readiness.

The test 2.

The four diesel generators shall continue for at shall be operable and there least a one-hour period shall be a minimum of 104,000 at rated load.

gal. of diesel fuel on site.

During the monthly generator 3.

The 4kV emergency buses test the diesel generator and the 480V emergency startlag air compressor load centers are energized.

shall be checked for operation'and its ability 4.

The four unit 125V batteries to recharge air receivers.

and their chargers shall be The operation of the operable.

diesel fuel oil transfer pumps shall be demonstrated, and the diesel starting time to reach rated voltage and frequency shall be logged.

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PBAPS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.9.B Operation with Inoperable 4.9.B Equipment Whenever the reactor is in Run Mode or Startup Mode with the reactor not in a Cold Condition, the availability of electric power shall be as specified in 3.9.A, except as follows :

1.

From and'after the date incoming power is not available from both Unit 3 startup transformers, or the Unit 2 startup transformer, or one emergency transformer, continued reactor operation is permissible for.

seven days.

During this period, the four diesel generators and associated emergency buses must be demonstrated to be operable.

2.

From and af ter the date that incoming power is not available from all three startup transformers or both emergency transformers, continued opera-tion is permissible, provided the four diesel generators and associated emergency buses are operable, all core and containment cooling systems are operable and reactor power level is reduced to 25% of the design.

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PBAPS

)

3.9 BA'SES

'The general objective of this Specification is to assure an adequate source of electrical power to operate the auxiliaries during plant operation, to operate facilities to cool and lubricate the plant during shutdown, and to operate the engineered safeguards following the accident.

There are four sources of ac electrical energy available; namely, two Unit 3 startup transformers, one Unit 2 startup transformer, and the diesel generators.

The de supply is required for switchgear and engineered safety feature systems.

Specification 3.9.A states the required availability of ac and de power; i.e.,

active off-site ac source and the required amount of on-site ac and de sources.

The diesel fuel supply consists of four (4) 35,000 gallon tanks.

Auxiliary power for PBAPS is supplied from three sources; the corresponding unit auxiliary transrormer, the Unit 2 startup transformer, and one of the Unit 3 startup transformers.

These transformers are sized to carry 100% of the auxiliary load.

If one of the startup transformers is lost, the unit can continue to operate since the unit auxiliary transformer is in service, the other startup transformer is available, and the required number of diesel generators is operational.

l If all three startup transformers are inoperable, the reactor power level must be reduced to a value whereby the units can safely reject the load and continue to supply auxiliary electric power to the station.

In the normal mode of operation, the Unit 2 startup transformer and one of the Unit 3 startup transformers are energized and four diesel generators are operable.

One diesel generator may be allowed out-of-service based on the availability of power from the startup transformer and the fact that three diesel generators carry sufficient engineered safeguards equipment to cover all I

breaks.

With the Unit 2 startup transformer and one diesel generator out-of-service, the off-site transmission line corresponding to the operable startup transformer and emergency transformer must be available.

With both Unit 3 startup transformers and one diesel generator out-of-service, the off-site transmission line corresponding to the operable startup transformer and emergency transformer must be available.

Upo,n the loss of one on-site and one off-site power source, power would be available from the other immediate off-site power source and the three operable on-site diesels to carry sufficient engineered safeguards equipment to cover all breaks.

In addition to these two power sources, removal of the Isolated Phase Bus

" quick" disconnect links would allow backfeed of power through the main transformer to the unit auxiliary transformer and provide power to carry the full station auxiliary load.

The time required to perform this operation is comparable to the time the reactor could remain on RCIC operation before controlled depressurization need be initiated.

A battery charger is supplied with each of the 125-Volt batteries.

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CERTIFICATE OF SERVICE I hereby certify.that copies of the foregoing Application were served on the following by deposit in the United States mail, first-class postage prepaid, on this 20th day of January, 1987.

Regional Administrator U.S. Nuclear Regulatory Commission, Region I 631 Park Avenue King of Prussia, PA 19406 T. P. Johnson, Resident Inspector U. S. Nuclear Regulatory Commission Peach Bottom Atomic Power Station P. O. Box 399 Delta, PA 17314 Mr. Thomas Gerusky, Director Bureau of Radiation Protection Department of Environmental Resources Fulton Bank Building, 5th Floor Third 6 Locusts Streets Harrisburg, PA 17120 i

/

Eu n,e J. Bradley Attorney for Philadelphia Electric Company