ML20198A232

Amend 179 to License DPR-35,revising TSs 3/4.5.F.1, Core & Containment Cooling Sys, to Extend Allowed Outage Time for Emergency Diesels

ML20198A232
Person / Time
Site:	Pilgrim
Issue date:	12/11/1998
From:	Thomas C NRC (Affiliation Not Assigned)
To:
Shared Package
ML20198A237	List: ML20198A232 ML20198A239
References
NUDOCS 9812160194
Download: ML20198A232 (18)

Text

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p2 2tg g7 UNITED STATES l

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NUCLEAR REGULATORY COMMISSION 4

WASHINGTON, D.C. 20066 4 001 49.....p BOSTON EDISON COMPANY DOCKET NO. 50-293 PILGRIM NUCLEAR POWER STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.179 License No. DPR-35

1. The Nuclear Regulatory Commission (the Commission or the NRC) has found that:

A.

The application for amendment filed by the Boston Edison Company (the licensee) i dated April 25,1996, as supplemented on September 5,1996, August 8,1997, March 26, July 31, and August 24,1998, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations; 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 and 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.

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9812160194 981211 PDR ADOCK 05000293 p

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Accordingty, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.B of Facility Operating License No.

DPR-35 is hereby amended to read as follows:

B.

Technical Soecifications The Technical Specifications centained in Appendix A, as revised through Amendment No.

179, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Tech ilcal Specifications.

3.

This license amendment is effective as of its date of issuance and shall be implemented within 30 days.

FOR THE NUCLEAR REGULATORY COMMISSION Cecil O. Thomas, Director Project Directorate 1-3 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date ofissuance: December 11, 1998 l

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ATTACHMENT TO LICENSE AMENDMENT NO.179 FACILITY OPERATING LICENSE NO. DPR-35 l

DOCKET NO. 50-293 l

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Replace the following pages of the Appendix A Technical Specifications with the attached pages.

The revised pages are identified by Amendment number and contain verticallines indicating the I

area of change.

Remove Insert 3/4.5-10 3/4.5-10 3/4.9-1 3/4.9-1 3/4.9-2 3/4.9-2 3/4.9-3 3/4.9-3 3/4.9-4 3/4.9-4 3/4.9-5 3/4.9-5 5.0-9 5.0-9 5.0-10 5.0-10 5.0-11 5.0-11 5.0-12 5.0-12 5.0 13 5.0-13 5.0-14 5.0-14 B3/4.5-22 B3/4.5-22 B3/4.5-23 B3/4.5-23 83/4.5-24 l

LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT 3.5 CORE AND CONTAINMENT 4.5 CORE AND CONTAINMENT 4

COOLING SYSTEMS (Cont)

COOLING SYSTEMS (Cont)

F.

Minimum Low Pressure Coolina and F.

Minimum Low Pressure Coolina and l

Diesel Generator Availabilltv Diesel Generator Availability

)

1. During any period when one

1. When it is determined that one i

emergency diesel generator EDG is inoperable, within 24 l

(EDG) is inoperable, continued hours, determine that the reactor operation is permissibis operable EDG is not inoperable l

only during the succeeding 72 due to a common cause failure, j

hours unless such EDG is sooner made operable, provided OR that all of the low pressure core and containment cooling perform surveillance 4.9.A.1.a systems shall be operable, and for the operable EDG' r

the remaining EDG shall be AND 2

operable in accordance with 3

4.5.F.1. If this requirement within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and once every 8 cannot be met, an orderly hours thereafter, verify correct l

shutdown shall be initiated and breaker alignment and Indicated the reactor shall be placed in power availability for each l

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the Cold Shutdown Condition offsite circuit, j

within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

2. Confirm the Station Black Out The 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> LCO can be esel enator(SBO4G) has extended to 14 days provided, in been demonstrated operable addition to the above within the preceding 7 days d

l requirements, the Station Black Out Diesel Generatoris verified OR operable in accordance with 4.5.F.2.

j within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> of declaring an

2. Any combination of inoperable EDG inoperable, perform a surveillance to demonstrate that components in the core and contalnment cooling systems the SBO-DG is operable.

shall not defeat the capability of AND the remaining operable

[

components to fulfill the cooling

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uncdons' within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> of demonstrating the SBO DG operability as specified

3. When irradiated fuelis in the above and once every 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> thereafter, verify normal breaker reactor vessel and the reactor is in the Cold Shutdown condition, connguration, both core spray systems, the LPCI and containment cooling systems may be inoperable, provided no work is being done which has the potential for draining the reactor vessel.

4. During a refueling outage, for a period of 30 days, refueling operation may continue provided that one core spray system or the LPCI system is operable or Specification 3.5.F.5 is met.

Amendment No. 179 3/4.5 10

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l LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQU.LREMENTS 3.9 AUXILIARY ELECTRICAL SYSTEM 4.9 AUXILIARY ELECTRICAL SYSTEM Anolicability Applicability Applies to the auxiliary electrical power Applies to the periodic testing system.

requirements of the auxiliary electrical systems.

Oblective:

Oblective To assure an adequate supply of Verify the operability of the auxiliary electrical power for operation of those electrical system.

systems required for safety.

1 Specification Soecification:

A.

Auxiliarv Electrical Eautoment

' A.

Auxiliarv Electrical Eauioment Surveillance The reactor sha!! not be made critical unless all of tha following conditions are 1.

DieselGenerators satisfied.

a.

Each diesel generator shallbe l

1.

Atleast one offsite transmission line and the startup transformer are manually started and loaded once each month to available and capable of demonstrate operational automatically supplying auxiliary readiness. The test shall power to the emergency buses.

continue for atleast a one hour period at rated load.

2.

An additional source of offsite power consisting of one of the During the monthly generator following:

test the diesel generator starting air compressor shall a.

A transmission line and be checked for operation and shutdown transformer capable of supplying power to its ability to recharge air receivers. The operation of the emergency 4160 voit the dieselfuel oiltransfer buses.

pumps shall be demonstrated, b.

The main transformer and and the dieselstarting time to unit auxiliary transformer reach rated voltage and available and capable of frequency shall be logged.

supplying power to the b.

Once per operating cycle the emergency 4160 voit buses.

condition under which the 3.

Both diesel generators shall be diesel generator is required will be simulated and test operable. Each diesel generator conducted to demonstrate that shall have a minimum of 19,800 gallons of diesel fuel on site.

It will start and accept the emergency load within the specified time sequence. The results shall be lopged.

PNPS 3/4.9 1 Amendment No.179 l

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LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REO REMENTS 3.9 AUXILIARY ELECTRICAL SYSTEM 4.9 AUXILIARY ELECTRICAL SYSTEM A.

Auxiliary Electrical Eculoment (Cont)

A.

Auxiliary Electrical Eautoment Surveillance (Cont)

I 1.

Verifying de-energization of the emergency buses arW load l

shedding from the eme gency i

buses.

2.

Verifying the diesel starts from ambient condition on the auto.

start signal, energizes the i

emergency buses with permanently connected loads, energizes the auto-connected emergency loads through the load sequence, and operates for 25 minutes whileits generatoris loaded with the emergency loads.~

During performance of this surveillance verify that HPCI and RCIC inverters do not trip.

The results shall be logged.

c.

Once per operating cycle with the dieselloaded per 4.9.A.1.b verify that on diesel generator trip, secondary (offsite) AC poweris automatically connected within 11.8 to 13.2 soconds to the emergency service buses and

'emergencyloads are energized through thetad sequencerin the same manner as describedin 4.9.A.1.b.1.

The results shall be logged.

PNPS 3/4.9 2 Amendment No.179 T~

klMITING CONDITIONS FOR OPER ATION SURVEILLANCE REQUlBEMENTS 3.9 AUXILIARY ELECTRICAL SYSTEM 4.9 AUXILIARY ELECTRICAL SYSTEM A.

Auxiliarv Electrical Eautoment (Cont)

Auxiliarv Electrical Eauioment Surveillance (Cont) 4.

4160 volt buses A5 and A6 are energized and the associated 480 d.

Ones a month the quantity of volt buses are energized.

diesel fuel available shall be logged.

5.

The station and switchyard 125 3'

and 250 volt batteries are operable.

e.

Once a month a sample of diesel Each battery shall have an fuel shall be checked for quality in operable battery charger, accordance with ASTM D4057-81 or D4177 82. The quality shall be 6.

Emergency Bus Degraded Voltage within the acceptable limits Annunciation System as specified specified in Table 1 of ASTM in Table 3.2.B.1 is operable.

D975-81 and logged.

s 7.

Specification:

2.

Station and Switchyard Batteries Two redundant RPS Electrical a.

Every week the specific gravity, the Protection Assemblies (EPAs) shall voltage and temperature of the be operable at all times on both pilot cell and overall battery voltage inservice power supplies.

shall be measured and logged.

AGH90 b.

Every three months the measurements shallbe made of a.

With one EPA on an inservice voltage of each cell to nearest 0.1 power supply inoperable, volt, specific gravity of each cell, continued operation is and temperature of every fifth cell.

permissible provided that the These measurements shallbe EPAis retumed to operable

logged, status or power is transferred.

to a source with two operable c.

Once each operating cycle, the 4

EPAs within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. If this stated batteries shall be subjected requirement cannot be met, to a Service Discharge Test (load trip the power source.

profile). The specific gravity and voltage of each cell shall be b.

With both RPS EPAs found to determined after the discharge and be inoperable on an inservice logged.

power supply, continued operation is permissible, d.

Once every five years, the stated provided at least one EPAis batteries shall be subjected to a restored to operable status or Performance Discharge Test power is transferred to a (capacity). This test will be source with at least one performed in lieu of the Service operable EPA within 30 Discharge Test requirements of minutes, if this requirement 4.9.A.2.0 above, cannot be met, trip the power source.

NOTE: Only applicable if tripping the power source would not result in a scram.

1 PNPS 3/4.9 3 Amendment No.179 m.f m

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LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIRRalEEE 3.9 AUXILIARY ELECTRICAL SYSTEM (Cont) 4.9 AUXILIARY ELECTRICAL S.YSTEM.(Cont) _

B.

Operation with fnocerable Eauloment Auxiliary Electrical Eauiome$t Surveillance (Cont)

Whenever the reactor is in Run Mode or Startup Mode with the reactor not in a 3

Emergency 4160V Buses AS-A6 Cold Condition, the availability of electric Degraded Voltage Annunciation power shall be as specified in 3.9.B.1, System.

3.9.B.2, 3.9.B.3, 3.9.B.4, and 3.9.B.S.

a.

Once each operating cycle, 1.

From and after the date that calibrate the alarm sensor, incoming power is not available from the startup or shutdown b.

Once each 31 days perform a transformer, continued reactor channel functional test on the operation is permissible under this alarm system.

condition for:

c.

In the event the alarm system

a. 3 days with the startup is determined inoperable transformer Inoperable under 3.b above, commence logging safety related bus E

voltage every 30 minutes until

b. 7 days with the shutdown such time as the alarm is transformer inoperable restored to operable status.

During this period, both diesel 4.

RPS Electrical Protection generators and associated Assemblies emergency buses must remain operable.

a.

Each pair of redundant RPS

- EPAs shall be determined to 2.

From and after the date that be operable at least once per incoming power is not available 6 months by performance of from both startup and shutdown an instrument functional test.

transformers, continued operation is permissible, provided both diesel b.

Once per 18 months each generators and associated pair of redundant RPS EPAs emergency buses remain operable, shall be determined to be all core and containment cooling operable by performance of systems are operable, reactor an instrument calibration and power levelis reduced to 25% of by verifying tripping of the design and the NRC is notified circuit breakers upon the within one (1) hour as required by simulated conditions for 10CFR50.72, automatic actuation of the protective relays within the 3.

From and after the date that one of following limits:

the diesel generators or associated emergency bus is made or found to Overvoltage s 132 volts be inoperable for any reason, Undervoltage 2.108 volts continued reactor operation is Underfrequency 2.57Hz permissible in accordance with Specifications 3.4.B.1,3.5.F.1, 3.7.B.1.c, 3.7 B.1.e, 3.7.B.2.c, and 3.7.B.2.e if Specification 3.9.A.1 and 3.9.A.2.a are satisfied.

PNPS 3/4.9-4 Amendment No.179 i

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LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.9 AUXILIARY ELECTRICAL SYSTEM (Cont) 4.9 AUXILIARY ELECTRICAL SYSTEM (Cont)

B.

Operation with inoperable Eouloment (Cont) 4.

From and after the date that one of the j

diesel generators or associated emergency buses and either the shutdown or startup transformer power source are made or found to be i

inoperable for any reason, continued reactor operation is permissible for 48 l

hours provided:

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a. The startup transformer and both i

offsite 345kV transmission lines.are

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available and capable of l

automatically supplying auxiliary l

power to the emergency 4160 volt l

buses, l

E

b. The 23kV transmission line and associated shutdown transformer are available and capable of automatically supplying auxiliary l

power to the emergency 4160 volt buses i

l S.

From and after the date that one of the 125 or 250 volt battery systems is made or found to be inoperable for any l_

reason, continued reactor operation is i

permissible during the succeeding three days within electrical safety considerations, provided repair work is initiated in the most expeditious manner to return the failed component to an operable state, and Specification 3.5.F is satisfied.

l 6.

With the emergency bus voltage less i

than 3958.5V but above 3878.7V (excluding transients) during normal operation, transfer the safety related buses to the diesel generators. If grid voltage continues to degrade be in at least Hot Shutdown within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and in Cold Shutdown within the following 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> unless the grid conditions improve.

l PNPS 3/4.9-5 Amendment No.179 L

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Programs cnd M:nuits 3

5.5 5.5 Programs and Manuals 5.5.7 Confiauration Risk Manaoement Proaram fCRMP)

CRMP provides a proceduralized risk-informed assessment to manage the risk associated with equipment inoperability The program applies to technical specification structures, systems, or components for which a risk informed allowed outage time has been granted.

The CRMP includes the fo!!owing elements:

a.

Provisions for the control and implementation of a Level 1 at power intemal event PRA informed methodology. The assessment is capable of evaluating the applicable plant configuration.

b.

_ Provisions for performing an assessment prior to entering the LCO Action Statement for preplanned activities.

c.

Provisions for performing an assessment after entering the LCO Action Statement for unplanned entry into the LCO Action Statement activities, d.

Provisions for assessing the need for additional actions after the discovery of additional equipment out of service conditions while in the LCO Action Statement.

e.

Provisions for considering other applicable risk significant contributors such as Level 2 issues and external events, quantitatively or qualitatively.

PNPS 5.0 9 Amendment No.179 l

Reporting Requiraments 5.6 5.0 ADMINISTRATIVE CONTROLS 5.6 Reporting Requirements The following reports shall be submitted In accordance with 10 CFR 50.4.

5.6.1 Occupational Radiation Exoosure Reoort A tabulation on an annual basis of the number of station, utility, and other personnel (including contractors) receiving exposures > 100 mrem /yr and their associated man rem exposure according to work and job functions (e.g., reactor i

operations and surveillance, inservice inspection, routine maintenance, special maintenance (including description), waste processing, and refueling). This tabulation supplements the requirements of 10 CFR 20.2206. The dose assignments to various duty functions may be estimated based on pocket dosimeter, thermoluminescent dosimeter (TLD), or film badge measurements.

Small exposures totaling < 20% of the individual total dose need not be accounted for, in the aggregate, at least 80% of the total whc!a body dose recel.*ed from extemal sources should be assigned to specific major work functionti. The report shall be submitted by April 30 of each year.

i 5.6.2 Annual Radioloalcal Environmental Ooeratino Reoort The Annual Radiological Environmental Operating Report covering the operation of the unit during the previous calendar year shall be submitted by May 15 of each year. The report shallinclude summaries, interpretations, and analyses of trends of the results of the Radiological Environmental Monitoring Program for the reporting period. The material provided shall be consistent with the objectives outlined in the Offsite Dose Calculation Manual (ODCM), and in 10 CFR 50, Appendix 1, Sections IV.B.2, IV.B.3, and IV.C.

The Annual Radiological Environmental Operating Reportshallinclude a summary of the results of analyses of all radiological environmental samples and of all environmental radiation measurements taken during the period pursuant to the locations specified in the table and figures in the ODCM, as well as summarized and tabulated results of these analyses and measurements in the format of the table in the Radiological Assessment Branch Technical Position, Revision 1, November 1979. In the event that some individual results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted in a supplementary report as soon as possible.

(continued)

PNPS 5.010 Amendment No.179 e.

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Reporting Requiramtnts 5.6 5.6 Reporting Requirements 5.6.3 Radioactive Effluent Release Reoort The Radioactive Effluent Release Report covering the operation of the und shall be submitted in accordance with 10 CFR 50.36a by May 15th of each year.

The report shallinclude a summary of the quantitles of radioactive liquid and gaseous effluents and solid waste released from the unit. The material provided shall be consistent with the objectives outlined in the ODCM and process control procedures and in conformance with 10 CFR 50.36a and 10 CFR 50, Appendix 1,Section IV.B.1.

5.6.4 Monthiv Ooeratino Reports Routine reports of operating statistics and shutdown experience shall be submitted on a monthly basis no later than the 15th of each month following the calendar month covered by the report.

5.6.5 Core Ooeratina Limits Reoort (COLR) a.

Core operating limits shall be established prior to each reload cycle, or prior to any remaining portion of a reload cycle, and shall be documented in the COLR for the following:

i 1.

Table 3.1.1 - APRM High Flux trip level setting 2.

Table 3.2.0 -APRM Upscale trip level setting 3.

3.11.A-Average Planar Unear Heat Generation Rate (APLHGR) 4.

3.11.B - Unear Heat Generation Rate (LHGR) 5.

3.11.C -Minimum Critical Power Ratio (MCPR) 6.

3.11.0 - Power / Flow Relationship During Power Operation 7.

4.2-Reactor Core b.

The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in the following documents:

1.

NEDE-24011-P A," General Electric Standard Application for Reactor Fuel," (the approved version at the time the reload analyses are performed shall be identified in the COLR).

(continued)

PNPS 5.0-11 Amendment No.179 4

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R: porting Requir:m:nts 5.6 5.6 Reporting Requirements 5.6.5 (continued) 2.

NEDC-31852P, " Pilgrim Nuclear Power Station SAFER /GESTR-LOCA Loss of Coolant Accident Analysis", dated September,1990 (the approved version at the time the reload analyses are performed shall be identified in the COLR), and 3.

NEDC-31312-P,

• ARTS Improvement Program Analyses for Pilgrim Nuclear Power Station', dated September 1987, (the approved version at the time the reload analyses are performed shall be identified in the COLR).

c.

The core operating limits shall be determined such that all applicable limits (e.g., fuel thermal mechanical limits, core thermal hydraulic limits,

- Emergency Core Cooling Systems (ECCS) limits, nuclear limits such as shutdown margin, transient analysis limits, and accident analysis limits) of the safety analysis are met.

d.

The COLR, including any midcycle revisions or supplements, shall be provided upon issuance for each reload cycle to the NRC.

PNPS 5.0 12 Amendment No.'179 l

High Radi: tion Arta I

5.7 5.0 ADMINISTRATIVE CONTROLS 5.7 High Radiation Area 5.7.1 Pursuant to 10 CFR 20, paragraph 20.1601(c), in lieu of the requirements of 10 CFR 20.1601, each high radiation area, as defined in 10 CFR 20, in which the Intensity of radiation is > 100 mrem /hr but < 1000 mrem /hr, shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring issuance of a Radiation Work Permit (RWP). Individuals qualified in radiation protection procedures (e.g., Health Physics personnel) or personnel continuously escorted by such individuals may be exempt from the RWP lasuance requirement during the performance of their assigned duties in high radiation areas with exposure rates 51000 mrem /hr, provided they are otherwise following plant radiation protection procedures for entry into such high radiation areas.

Any individual or group of individuals permitted to enter such areas shall be provided with or accompanied by one or more of the following:

a.

A radiation monitoring device that continuously indicates the radiation dose rate in the area.

b.

A radiation monitoring device that continuously integrates the radiation dose rate in the area and alarms when a preset integrated dose is received. Entry into such areas with this monitoring device may be made after the dose rate levels in the aren have been established and personnel are aware of them.

c.

An individual qualified in radiation protection procedures with a radiation dose rate monitoring device, who is responsible for providing positive control over the activities within the area and shall perform periodic radiation surveillance at the frequency specified by the Radiation Protection Manager in the RWP.

5.7.2 in addition to the requirements of Specification 5.7.1, areas with radiation levels

t 1000 mrem /hr shall be provided with locked or continuously guarded doors to prevent unauthorized entry and the keys shall be maintained under the administrative control of the Nuclear Watch Engineer on duty or health physics supervision. Doors shall remain locked except during periods of access by personnel under an approved RWP that shall specify the dose rate levels in the immediate work areas and the maximum allowable stay times for individuals in those areas. In lieu of the stay time specification of the RWP, direct or remote (such as rlosed circuit TV cameras) continuous surveillance may be made by (continued)

PNPS 5.0-13 Amendment No.179

l High Radiation Area 5.7 l

5.7 High Radiation Area l

5.7.2 (continued) l personnel qualified in radiation protection procedures to provide positive l

exposure control over the activities being performed within the area.

5.7.3 For individual high radiation areas with radiation levels of > 1000 mrem /hr, i

l accessible to perronnel, that are located within large areas such as reactor containment, where no enclosure exists for purposes of locking, or that cannot l

be continuously guarded, and where no enclosure can be reasonably constructed around the individual area, that individual area shall be barricaded and conspicuously posted, and a flashing light shall be activated as a warning device.

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l (continued)

PNPS 5.0 14 Amendment No.179 l

Minimum Lew PrG suro Cocling End Dieoil Genirattr Avall bility 3/4.5.F B 3/4.5 CORE AND CONTAINMENT COOLING SYSTEMS 3/4.5.F.

Minimum Low Pressure Cooling and Diesel Generator Availability BASES l

BACKGROUND The purpose of Specification 3/4.5.F is to assure that adequate core cooling equipment is available at all times. If, for example, one core spray were out of service and the diesel which powered the opposite core spray were out of service, only 2 LCPI pumps would be available.

It is during refueling outages that major maintenance is performcd and during such time that all low pressure core cooling systems may be out of service. This specification provides that should this occur, no work will be performed on the primary system which could lead to draining the vessel. This work would include work on certain control rod drive components and recirculation system.

Specification 3.4.F.5 allows removal of one CRD mechanism while the torus is in a dralned condition without compromising core cooling

- capability. The available core cooling capability for a potential drain!ng of the reactor vessel while this work is performed is based on an estimated drain rate of 300 gpm if the control rod blade sealis unseated. Flooding the refuel cavity and dryer / separator pool to elevation 114' 0* corresponds to approximately 305,000 gallons of water and will provide core cooling capability in the event leakage from the control rod drive does occur. A potential draining of the reactor vessel (via control rod blade leakage) would allow this water to enter into the torus and after approximately 243,000 gallons have l

l accumulated (needed to meet minimum NPSH requirements for the LPCI and/or core spray pumps), the torus would be able to serve as a common suction header. This would allow a closed loop operation of the LPCI system and the core spray system (once re-aligned) to the torus, in addition, the other core spray system is lined up to the condensate sta-m tanks which can supplement the refuel cavity and dryer / separator p % water to provide core flooding,if required.

ACTION The maximum allowed out-of service (OOS) time for one EDG is 14 days, provided that one EDG and the SBO-DG are operable, in addition to all of the low pressure core and containment cooling systems as specified in 3.5.F.1.-If the SBO-DG is determined to be inoperable, the maximum allowed OOS time for one EDG is 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. A 24-hour LCO will control the plant for cold shutdown if the SBO-DG becomes inoperable anytime after 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> during a 14-day EDG LCO.

SURVEILLANCE The SBO-DG shall be determined to be operable as defined below for extending the 3 days OOS time to 14 days for an EDG. The SBO DG is operable if a surveillance was completed within the last seven days before extending to a 14-day OOS; otherwise, a surveillance must be completed to demonstrate that the SBO-DG is operable. The 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> period allows the operators to complete the required SBO DG surveillance using the 23Kv offsite power source and to notify Commonwealth Electric of the needed use of the 23Kv line in the testing configuration. The SBO-DG is operable if it is capable of PNPS B3/4.5-22 Amendment No.179

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Minimum Low Pres:ure Cooling cnd Dl;c"I Cen:r;t:r Av;ll:bility 3/4.5.F

(

O 3/4.5 CORE AND CONTAINMENT COSLIN3 SYSTEMS l

SURVEILLANCE energizing the safety bus associated with the Inoperable EDG. Within

)

l (continued) one hour of demonstrating SBO DG operability and once every eight l-hours thereafter, the normal breaker configuration for energizing the l

safety bus associated with the inoperable EDG should be verified. The SBO DG is a non safety-related, manually started,2000KW generator and is not a qualified replacement for an EDG.

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l 3/4.5.G.

Deleted l~

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PNPS B3/4.5 23 Amendment No.179 l

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Maintin;ntra cf Fill;d D!sch:rg) Pipe 3/4,5.H B 3/4.5 CORE AND CONTAINMENT COOLING SYSTEMS 3/4.5.H.

Maintenance of Filled Discharge Pipe BASES BACKGROUND If the discharge piping of the core spray, LPCI system, HPCI, and RCIC are not filled, a water hammer can develop in this piping when the pump and/or pumps are started. An analysis has been done which shows that if a water hammer were to occur at the time at which the l

system were required, the system would still perform its design l

function. However, to minimize damage to the discharge piping and to l

ensure added margin in the operation of these systems, this Technical Specification requires the discharge lines to be filled whenever the system is in an operable condition.

SURVEILLANCE An acceptable method of ensuring that the lines are fullis to vent at the high points. The monthly frequency is based on the gradual nature of void buildup in the ECCS piping, the procedural contrc'a, and operadng l

experience.

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PNPS B3/4.5 24 Amendment No. 179

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