Text

Amends 147 & 83 to Licenses DPR-57 & NPF-5,respectively, Modifying Tech Specs Re Testing of Onsite Emergency Diesel Generators
	ML20237K230
Person / Time
Site:	Hatch
Issue date:	08/25/1987
From:	Hood D; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20237K233	List: ML20237K230; ML20237K235; ML20237K247;
References
	GL-84-15, TAC-55865, TAC-55866, NUDOCS 8708270108
	Download: ML20237K230 (28)
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UNITED STATES 8.

NUCLEAR REGULATORY COMMISSION

.h' WASHINGTON, D. C 20555 W'

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p GEORGIA POWER COMPANY OGLETHORPE POWER CORPORATION MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA CITY OF DALTON, GEORGIA DOCKET NO. 50-321 EDWIN 1. HATCH NUCLEAR PLANT, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 147 License No. DPR-57 1.

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

A.

The application for amendment to the Edwin I. Hatch Nuclear Plant, Unit 1 (the facility) Facility Operating License No. DPR-57 filed by. Georgia Power Company, acting for itself. Oglethorpe. Power Corporation, Municipal Electric Authority of: Georgia, and City of Dalton, Georgia, (the licensee) dated March 31, 1986, 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 confonnity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.

There is reasonable assurance (i) that the activities authorized by 1

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 Comission's regulations set forth in 10 CFR Chapter I; 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; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 i

of the Comission's regulations and all applicable requirements have been satisfied.

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Accordingly, the license is amended by changes to the Technical Specifi-cations as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-57 is hereby amended to read as follows:

(2)

Technical Specifications 1

The Technical Specifications contained in Appendices A and B, as 1

revised through Amendment No.147, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.- ' This license amendment is effective as of its date of issuance and shall be implemented within 60 days of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION l

\\@

Darl S. Hood, Acting Director Project Directorate II-3 Division of Reactor Projects-I/II

Attachment:

Changes to the Technical Specifications Date of Issuance:

August 25, 1987 l

956 PD#[I-j/DRP-I/II PD#II-3/DRP-1/II

-0GC-hesda PD#II-3/DRP-I/II MDudfad/mac LCrocker

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O'M( h DHood, Acting Director 08/3 /87 08/p /87 08/

87 08/ p /87

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ATTACHMENT TO LICENSE AMENDMENT NO. 147 FACILITY.0PERATING LICENSE NO. DPR-57 DOCKET NO. 50-321 i

Replace the'following pages of the Appendix A Technical Specifications with the enclosed pages.- The revised pages are identified by amendment ' number and contain vertical lines indicating the areas of change.

Remove Insert Page Page 1.0-10 1.0-10 3.5-2 3.5-2 i

3.5-3 3.5-3 3.5-4 3.5-4 3.5-6 3.5-6 3.5-10 3.5-10 20' 3.5-10a 3.5-12 3.5-12 3.5-13 3.5-13 3.5-14 3.5-14 3.5-15 3.5-15 3.9-1 3.9 I 3.9-2 3.9-2 3.9-2a 3.9-5 3.9-5 3.9-6b I

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1.0 D,EFINITIONS (Continued)

EEE. MILK ANIMAL A cow or goat that is producing milk for human 4

consumption.

FFF. DOSE EQUIVALENT IODINE' The DOSE EQUIVALENT I-131 shall be that concentration of I-131 (microcurie / gram), which alone would produce the same thyroid dose as the quantity and isotopic mixture of I-131, I-132, I-133, I-134, and I-135 actually present.

.The tyroid dose conversion f actors used for this calculation shall be those listed in table III of TID-14844 or those in NRC Regulatory Guide 1.109, Revision 1, October 1977 GGG. ACTION ACTION shall be that part of a specification which prescribes remedial measures required under designated conditions.

HHH.

CHANNEL CHECK A CHANNEL CHECK shall be the qualitative assessment of f

channel behavior during operation by observation. This determination shall include, where possible, comparison of f

the channel indication and/or status with other

/

indications and/or status derived from independent

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Y instrument channels measuring the same parameter.

III.

STAGGERED TEST BASIS STAGGERED TEST BASIS shall consist of:

)

A test schedule for n systems, subsystems trains or a.

other designated components obtained by dividing the j

specified test interval into n equal subintervals, f

b.

The testing of one system, subsystem, train or other designated components at the beginning of each subinterval.

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i Amendment No. 147 HATCH - UNIT 1 1.0-10 1

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' LIMITING CONDTIONS FOR OPERATION SlTRVEILLANCE REOUIRD!ENTS 3.5.A.2.

Operation with Inoperable 4.5.A.i.

[ surveillance with Inoperable Components, Components If one CS system loop is inoper-When it is determined that one able, the reactor may remain in core spray loop is inoperable operation for a period not to at a time when operability is exceed seven (7) days providing required, the other core spray all active components in the loop, and the RHR system LPCI other CS system loop, the RHR mode shall be demonstrated to system LPCI mode and the diesel be operable immediately. The generators (per Specification operable core spray loop shall 4.9. A.2.a) are operable, be demonstrated to be operable daily until both loops are returned to normal operation.

3.

Shutd9wn Requirements If Specification 3.5.A.1.a or 3.5.A.2. cannot be met thi'~

reactor shall be placed in the Cold Shutdown Condition within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

B.

Residual Heat Removal (RHR)

B.

Residual Heat Removal (RHR)

System (LPCI and Containment System (LPCI and Containment Cooling Mode)

Cooling Mode) 1.

Normal System Availability 1.

Normal Operational Tests RHR system testing shall be performed as follows:

Item Frequency a.

The RHR System shall be operable:

a. Air test on Once/5 years drywell head-(1) Prio-to reactor startup ers and nozzles from a cold condition, or and air or water test on (2) When irradiated fuel is in torus headers the reactor vessel and the and nozzles

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reactor pressure is greater

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than atmospheric except as stated in Specification 3.5.B.2.

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. HATCH - UNIT 1 3.5-2 Amendment No. 147

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3.5.B.1.

Normal System Availability (Cont.)

4.5.B.1.

Normal Operational Tests One RER loop with two pumps or two Item Frecuency loops with one pump per loop shall be operable in the shutdown cooling

b. Simulated Once/ Operating mode when irradiated f uel is in the Automatic Cycle reactor vessel and the reactor pres-Actuation sure is atmospheric except prior to Test a reactor startup as stated in Speci-fication 3.5.B.1.a.

c. The reactor shall not be started up

c. System flow Once/3 months with the RHR system supplying rate: Each cooling to the fuel pool.

RHR Pump shall deliver

d. During reactor power operation, the at least 7700 LPCI system discharge cross-tie gpm against a valve, E11-F010, shall be in the system head of closed position and the associated at least 20 psig.

valve motor starter circuit breaker shall be locked in the

d. Pump Opera-Once/ month off position. In addition, an bility annunciator which indicat&s'that the cross-tie valve is not in the

e. Motor Oper-Once/ month fully closed position shall be ated valve available in the control room.

operability

e. Both recirculation pump discharge

f. Both recirculation pump discharge valves shall be operable prior to valves shall be tested for oper-reactor startup (or closed if per-ability during any outage exceeding mitted elsewhere in these speci-48 hours, if operability tests have f ications).

not been perf ormed during the preceding month.

2. Operation with Inoperable

2. Surveillance with Inoperable Components Components

a. One LPCI Pump Inoperable

a. One LPCI Pump Inoperable If one LPCI pump is inoperable, the When one LPCI pump is inoperable reactor may remain in operation for the remaining LPCI pumps and asso-a period of not to exceed seven (7) ciated flow paths, and the Core days provided that the remaining Spray system shall be demonstrated LPCI pumps, both LPCI subsystem to be operable immediately and flow paths, the Core Spray system, daily thereaf ter, until the inoper-and the associated diesel genera-able LPCI pump is restored to tors are operable (per Specifica-normal service.

tion 4.9.A.2.a).

b. One LPCI Subsystem Inoperable

b. One LPCI Subsystem Inoperable A LPCI subsystem is considered to When one LPCI subsystem is inoper-to be inoperable if (1) both of the able, all active components of the LPCI pumps within that system are remaining LPCI subsystem and the inoperable or (2) the active Core Sp' ray system shall be demon-valves in the subsystem flow path strated to be operable, immediately are inoperable.

HATCH - UNIT 1

3. 5-3 Amendment No. 147

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LIMITING CONDTIONS FOR OPERATION SLTRVEILLANCE REQUIREMENTS 3.5.B.2.

Operation with Inoperable 4.5.B.2.

Surveillance with Inoperable Components (Continued)

Components (Continued) b.

If one LPCI subsystem is inoper-and daily thereaf ter, until the able, the reactor may remain in inoperable.LPCI subsystem is operation for a period not to restored to normal service.

exceed seven (7) days provided that all active components of the remaining LPCI subsystem, the Core Spray system, and the associated diesel generators are operable (per Specification 4.9.A.2.a).

HATCH - UNIT 1

3. 5-4 Amendment No. 147

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LIMITING CONDTIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.5'.C.3." Two Pumps Inoperable 4.5.C.3.

Two Pumps Inoperable If two RHR service water pumps are When two RHR service water pumps j,

inoperable, the reactor may re-are inoperable, the remaining i

main in operation for a period operable RHR service water sub-not to exceed seven (7) days pro-systems shall be demonstrated vided all. redundant active com-to be operable immediately ponents in both of the RHR and daily there&f ter for seven (7) service water subsystems are days or until the inoperable

. operable.

.omponents ar'e returned to normal' operation.

4.

Shutdown Requirements If Specifications 3.5.C cannot be met, the reactor shall be placed in the Cold Shut-down Condition within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

D. High Pressure Coolant Injection D. High Pressure Coolant Injection (HPCI) System (HPCI) System 1.

Normal System Availability

1. Normal Operational Tests HPCI system testing shall be performed as follows:

Item Frequency

a. The HPCI System shall be

a. Simulated Once/ Operating operable:

cutomatic Cycle actuation

1. Prior to reactor startup test from a cold condition, or

2. When irradiated fuel is in the reactor vessel and the reactor pressure is greater than 150 psig, except as stated in Specification

3. 5. D. 2. *

b. Flow rate at Once/3 months normal reactor vessel oper-ating pressure and Flow rate at Once/ Operating 150 psig Cycle reactor

HPCI is not required to be operable for perfopfgggpr8f inservice hydrostatic or leak testing with reactor pressure greater than 150 psig and all control HATCH 5 kbubf3f#

3.5-6 Amendment No. 147 u.... u..

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1, LIMITING CONDTIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.5.G.. Minimum Core'and Containment 4.5.G.

Surveillance of Core and Contain-Cooling System Availability ment Cooling Systems Ddring any period when one of Wen it is determined that one i

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l the standby diesel. generators-of the standby diesel generators-is inoperable,. continued reactor is inoperable,. all of the compo-i operation'is limited tp seven (7)

-nents in the RHR system LPCI' i

days unless operability.of the mode and containment' cooling

. diesel generator is restored.

mode connected to the operable within this period.

During such diesel generators shall be de-seven (7) days all of the com-monstrated to.be operable im.

ponents in the RHR. system LPCI mediately and daily thereafter.

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mode.and containment cooling mode shall be operable. If this requirement cannot.be met, an orderly. shutdown shall be ini-tiated and'the reactor shall be' in the Cold Shutdown Condition within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .. Specification

.3.9 provides further guidance on electrical system availability.

Any combination of inoperable components in the core and con-tainment cooling' systems shall not defeat the capability of the remaining operable components

'l to fulfill'the core and contain-ment cooling functions.

W en. irradiated fuel is in the reactor vessel and the reactor is in the Cold Shutdown Condition, both-core spray

' systems and'the LPCI and containment cooling subsystems'of the RHR system may be inoperable provided that the shut-down cooling' subsystem of the RHR system is operable in accordance with Specification 3.5.B.1.b and that no work is being done which i

has the potential for draining the reactor vessel.

i HATCH - UNIT 1 3.5-10 Amendment No. 147 l

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LIMITING CONDTIONS FOR OPERATION SURVEILLANCE REQUIREMENTS H.

Maintenance of Filled Discharge H. Maintenance of Filled Discharge Pipes.

Pipes Whenever the core spray system, The following surveillance re-LPCI, HPCI, or RCIC are required

'quirements shall be performed to be operable,.the' discharge' pip-to assure that.the discharge l

ing from the pump discharge of these piping of the core spray sys-systems to the last block valve tem, LPCI, HPCI, and RCIC are shall be filled.. The suction of the filled when required:

HPCI pumps shall be' aligned to the condensate storage tank.

1. Every month prior to the testing of the LPCI and core spray systems, the" dis-charge piping of these systems shall be vented

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HATCH - UNIT 1 3.5-10a Amendment No. 147

' LIMITING CONDTIONS FOR OPERATION SURVEILLANCE REQUIREMENTS

'3.5.J. Plant Service Water Systems 4.5.J.

Plant Service Water System

1. Normal Availability

1. The automatic pump start functions sad automatic The reactor shall not be isolation functions shall made critical from the be tested once per operating cold shutdown condition cycle.

unless the Plant Service I

Water System (including 4 plant service water pumps and the standby service I

water pump) is operable.

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2. Inoperable Components

2. Inoperable Components a.The standby service water

a. With the standby service pump may be inoperable for water subsystem inoperable a period not to exceed 60 for up to 60 days, provide days provided that an alter-Unit 1 service water cooling nate Unit 1 plant service to the 1B diesel generator water cooling source to,the by verifying OPERABILITY of an 1B diesel generator is alternate Unit i service water OPERABLE.

cooling source within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

Otherwise, declare the 1B diesel generator inoperable and take the action required by Specification 3.9.B.2.

b.One PSW pump may be in-

b. When one PSW pump is made operable for a period not or found to be inoperable, to exceed 30 days provided the standby service water all diesel generators are pump, the three remaining operable per Specification PSW pumps, and both PSW 4.9.A 2.a.

divisions shall be demon-strated to be operable immediately and weekly thereafter.

c.One PSW pump and the stand-

c. When one PSW pump and the

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by service water pump may standby service water pump be inoperable for a period are made or found to be not to exceed 30 days pro-inoperable, the three re-vided all diesel generators maining PSW pumps, and both are operable per Specification PSW divisions shall be 4.9.A.2.a.

demonstrated to be operable immediately and weekly thereafter.

d.Two PSW pumps or one PSW

d. When two PSW pumps or one PSW division may be inoperable for division are made or found to a period not to exceed 7 days be inoperable, the standby provided the diesel generators service water pump and all associated with the operable active components of the PSW components are operable operable division or divi-per Specification 4.9.A.2.a.

sions shall be demonstrated to be operable immediately HATCH - UNIT 1 3.5-12 and daily thereaf ter.

Amendment No. 147

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LIMITING CONDTIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.5.J. Plant Service Water Systems 4.5.J.

Plant Service Water System

2. Inoperable Components (Cont'd)

e. Two PSW pumps or one PSW

e. When two PSW pumps or one division, and tbe standby PSW division, and the service water pump may be in-standby service water pump operable for a period not to are made or found to be exceed 7 days provided the inoperable, all active diesel generators associated components of the operable with the operable PSW com-division or divisions shall ponents are operable per l

be demonstrated to be Specification 4.9.A.2.a.

l operable immediately and daily thereafter.

For each condition above in which the standby service water pump is inoperable, cooling water to diesel generator 1B shall be intertied with the PSW divisional piping supply.

When cooling water to diesel 3.

Shutdown Requirements generator 1B is intertied with the PSW divisional If the requirements of Specifications piping supply, operability 3.5.J.1 and 3.5.J.2 cannot be met of the divisional interlock the reactor shall be placed in the valves shall be demonstrated.

cold shutdown condition within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

3.5.K. Equipment Area Coolers 4.5.K.

Equipment Area Coolers 1.

The equipment area coolers

1. Each equipment area cooler serving the Reactor Core Iso-is operated in conjunction lation Cooling (RCIC), High with the equipment served by Pressure Coolant Injection that particular cooler; (HPCI), Core Spray or Residual therefore, the equipment area Heat Removal (RRR) pumps must coolers are tested at the be operable at all times when same frequency as the pumps the pump or pumps nerved by which they serve.

that specific cocter is con-sidered to be operchie.

2.

When an equipment area cooler is not operable, the pump (s) served by that cooler must be considered inoperable for Technical Specification purposes.

HATCH - UNIT 1 3.5-13 Amendment No. 147

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BASES FOR LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3.5.

CORE AND CONTAINMENT COOLING SYSTEMS A.

Core Spray (CS) System

1. Normal System Availability Analyses presented in Section 6 of the FSAR and Appendix I of the HNP-2 PSAR demonstrated that the core spray cystem provides adequate cooling to the core to dissipate the energy associated with the loss-of-coolant accident and to limit fuel clad temperature to below 2,3000F which assures that core geometry remains intact and to limit any clad metal-water reaction to less than one percent. Core spray distribution has been shown in tests of systems similar in design to HNP-1 to exceed the minimum requirements.

In addition, cooling effectiveness has been demonstrated at less than half the rated flow in simulated fuel assemblies with heater rods to duplicate the decay heat characteristics of irradiated fuel.

TheintentoftheCSshstemspecificationsistopreventoperationabove atmospheric pressure without all associated equipment being operable.

However, during operation, certain components may be out of service for the specified allowable repair times. The allowable repair times have been selected using engineering judgment based on experiences and supported by availability analysis. Assurance of the availability of the remaining systems is increased by demonstrating operability immediately and by requiring-selected testing during the outage period.

When the reactor vessel pressure is atmospheric, the limiting conditions for operation are less restrictive. At atmospheric pressure, the minimum requirement is for one supply of makeup water to the core. Requiring two operable RHR pumps and one CS pump provides redundancy to ensure makr.up water availability.

2. Operation with Inoperable Components Should one core spray loop become inoperable:

the remaining core spray loop and the RHR system are demonstrated to be operable to ensure their availability should the need for core cooling arise. These provide extensive margin over the operable equipment needed for adequate core cooling. With due regard for this margin, the allowable repair time of 7 days was chosen.

B.

Residual Heat Removal (RHR) System (LPCI and Containment Cooling Mode)

1. Normal System Availability The RHR system LPCI mode is designed to provide emergency cooling to the core by flooding in the event of a loss-of-coolant accident. This system is completely independent of the core spray system; however, it does function in combination with the core spray system to prevent excessive L

fuel clad temperature. The LPCI mode of the RHR system and the core spray system provide adequate cooling for break areas of approximately 0.2 square feet up to and including the double-ended recirculation line break without assistance from the high-pressure emergency core cooling systems.

HATCH - UNIT 1 3.5-14 Amendment No. 147 x.--

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3.5.B.1.

Normal System Availability (Continued)

Observation of the stated requirements for the containment cooling mode assures that the suppression pool and the drywell will be sufficiently cooled, following a loss-of-coolant accident, to prevent primary contain-ment overpressurization. The containment cooling function of the RHR system is permitted only af ter the core has reflooded to the two-thirds core height level. This prevents inadvertently diverting water needed f or core flooding to the less urgent task of containment cooling. The two-thirds core height level interlock may be manually bypassed by a keylock switch.

The intent of the RHR system specifications is to prevent operation above atmospheric pressure without all associated equipment beint, oper-able. However, during operation, certain components may be out of service for the specified allowable repair times. The allowable repair times have been selected using engineering judgment based on experiences and supported by availability analysis. Assurance of the availability of the remaining systems is increased by demonstrating operability immediately and by requir,ing selected testing during the outage period.

When the reactor vessel pressure is atmospheric, the limiting conditions for operation are less restrictive. At atmospheric pressure, the minimum requirement is for one supply of makeup water to the core.

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2. Operation with Inoperable Components With one LPCI pump inoperable or one LPCI subsystem inoperable, adequate core flooding is assured by the demonstrated operability of the redundant LPCI pumps and LPCI subsystem, and the Core Spray system. The reduced redundancy justifies the specified 7 day out-of-service period.

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l RATCH - UNIT 1 3.5-15 Amendment No. 147

LIMITING CONDTIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.9. AUXILIARY ELECTRICAL SYSTEMS 4.9.

AUXILIARY ELECTRICAL SYSTEMS Applicability Applicability The Limiting Conditions for The Surveillance Requirements apply Operation apply to the auxiliary to the periodic testing require-electrical power systems.

ments of the auxiliary electrical power systems.

Objective Objective The objective of the Limiting Conditions for Operation is to The objective of the Surveillance assure an adequate supply of Requirements is to verify the electrical power for operation of operability of the auxiliary those systems required for safety.

electrical systems.

Specifications Specifications A. Requirements for Reactor A.

Auxiliary Electrical Eystems Startup Equipment

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The reactor shall not be made Tests shall be performed at sched-critical from the Cold Shutdown uled intervals as follows to de-Condition unless all of the fol-tect deterioration of equipment lowing conditions are satisfied:

and to demonstrate that auxiliary electrical systems equipment and components are operable.

t 1.

Offsite Power Sources 1.

Offsite power Sources At least two 230 kV offsite trans-Verify correct breaker mission lines shall be available alignments and indicated power and each shall be capable of availability at least once supplying auxiliary power to the per 7 days.

emergency 4160 volt buses (1E, 1F, and 1G) and each shall be j

capable of supplying power to both startup auxiliary trans-formers (1C and 1D).

2.

Standby AC ' Power Supply (Diesel 2.

Standby AC Power Supply (Diesel Generators lA, 1B, and IC)_

Generators 1A, 1B, and IC)

Three diesel generators 1A, 1B The fo11 ewing periodic tests and and 1C) shall be operable and surveillance of the standby AC capable of supplying power to power supply (Diesel Generators the emergency 4160 volt buses 1A,1B, and 10) shall be per-(1E, 1F, and 1G).

formed : -

For each diesel generator to be operable and capable of sup-plying power, the following conditions must be met:

RATCH - UNIT 1 3.9-1 Amendment No. 147

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LXMITING CONDTIONS FOR OPERATION SURVEILLANCE REQUIREMENTS l

3.9. A.2. ' Standby AC Power Supply (Diesel 4.9.A.2. Standby AC power Supply (Diesel Generators LA, 1B, and IC)

Generators LA, 1B, and IC)

(Contintued)

(Continued)

a. Operability

a. Operability The diesel generator itself and its auxiliaries are operable.

1.Each diesel generator shall be manually started and loaded to demonstrate operational readiness in accordance with the frequency specified in Table 4.9-1 on a Staggered Test Basis.

Verify that each diesel starts from ambient condition, gradually load the generator to 1710-2000 KW8 and operate fer > 60 minutes.

During the generator test, the starting air compressor shall be checked for operation and for its ability to recharge the air system.

2.At least once per 184 days, each diesel generator shall be started and verified to reach sychronous speed in < 12 seconds, loaded to an indicated 2250-2400 KW* for 1A and 1C and 2360-2425 KW* for 1B l

in < 120 seconds, and operated for > 60 minutes.

b. Diesel Battery (125 Volt)

b. Diesel Battery (125 Volt)_

Each 125 volt diesel battery Each 125 voit diesel battery is operable and capable of shall be subjected to the supplying the required load.

same periodic surveillance as the plant batteries in Speci-fication 4.9.A.3.

c. Battery Charger

c. Battery Charger An opera,ble battery charger is indicators shall be provided available. Each battery charger to monitor the status of shall have adequate capacity to the battery charger supply, restore its battery to full This instrumentation shall charge within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months from a include indication of output j

discharged condition while current and output voltage.

l carrying the DC load.

d. Diesel Fuel

d. Diesel Fuel There shall be a minimum of Each month the quantity of 80,000 gallons of acceptable diesel fuel available in each diesel fuel in the diesel fuel storage tank shall be fuel storage tanks.

measured and recorded.

Momentary variations outside this band shall not invalidate HATCH - UNIT 1 3.9-2 the test.

Amendment No. 147 n..

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b LIMITING CONDTIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 4.9. A.2.Standbv AC Power Supply Diesel Generators lA, 1B, and IC)

(Continued)

d. Diesel Fuel (Cont'd)

At least once per 92 days by verifying that a sample of diesel fuel from the fuel storage tank, obtained in accordance with ASTM-D-270-65, is within the acceptable limits specified in Table 1 of ASTM D975-74 when checked for viscosity, water and sediment.

e. Fuel Oil Transfer Pumps The operation of the diesel fuel oil transfer pumps shall be demonstrated once each month.

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HATCH - UNIT 1 3.9-2a Amendment No. 147

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t LIMITING CONDTIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.9.B.1.

One Startup Auxiliary Transformer 4.9.B.1. One Startup Auxiliary Transf ormer (lC or 1D) Inoperable or Only One (1C or 1D) Inoperable or Only One Off site Power Source Available Off site Power Source Available (230 kV Transmission Line)

(230 kV Transmission Line)

Reactor operation is permissible When it is established that one for seven days from the date that startup auxiliary transformer l

one startup auxiliary transformer (1C or 1D) is inoperable or in-(1C or 1D) is inoperable or in-coming power is available f rom coming power is available from only one 230 kV off site trans-only one 230 kV off site trans-mission line, verify correct breaker mission line provided the in-alignments and indicated power creased Surveillance Require-availability within one hour and ments as stated in Specification at least once per eight hours there-4.9.B.1 are implemented.

af ter, and perform Surveillance Requirements 4.9.A.2.a within 24 l

hours.

2.

One Diesel Generator (1A,1B, 2.

One Diesel Generator (1A, 1B, or 1C) Inoperable or 1C) Inoperable From and af ter the date that one When it is established that one of the diesel generators is made diesel generator (1A,1B, or IC) l or found to be inoperable, continued is inoperable, verify correct breaker reactor operation is permissible in alignments and indicated power accordance with Specification 3.5.G availability within one hour and for a period not to exceed seven at least once per eight hours there-days provided that two 230 kV off site af ter, and perf orm Surveillance transmission lines are available, Requirement 4.9.A.2.a within 24 both remaining diesel generators hours, and every 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months thereaf ter.

and associated emergency buses are operable, and the increased Surveillance Requirements as stated in Specification 4.9.B.2,are implemented.

3.

One 125/250 Volt DC Power System 3.

One 125/250 Volt DC Power System (Plant Battery 1A or 1B) Inoper-(Plant Battery 1A or 1B) Inoper-able able From and af ter the date that one When it is established that one of of the two 125/250 voit plant bat-the 125/250 voit DC power systems teries is made or f ound to be in-(plant battery 1A or 1B) is made operable, continued reactor oper-or found to be inoperable, the ation is permissible during the pilot cell voltage and specific succeeding seven (7) days within gravity and the overall battery electrical safety considerations, voltage of the operable plant bat-provided repair work is initiated tery shall be tested daily and de-immediately to return the f ailed termined to be satisf actory, component to an operable state, Specification 3.5.G is satisfied, HATCH UNIT 1 3.9-5 Amendment No. 147

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Table 4.9-1 DIESEL GENERATOR TEST SCHEDULE Number of Failures In Last 20 Valid Tests

Test Frequency g1 At least once per 31 days

2. 2 At least once per 7 days

. - ~.

4 l

l l

l 0 Criteria for determining number of failures and number of valid tests shall be in accordance with Regulatory Position C.2.e of Regulatory Guide 1.108, Revision 1, August 1977, except that only the last 20 tests are used, and are determined on a per diesel basis.

HATCH - UNIT 1 3.9-6b Amendment No. 147

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4 UNITED STATES '

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g NUCLEAR REGULATORY COMMISSION E-WASHINGTON, D. C. 20555 g w../

1 GEORGIA' POWER COMPANY-I l

'0GLETHORPE POWER CORPORATION MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA l

CITY OF DALTON, GEORGIA DOCKET NO. 50-366 EDWIN 1. HATCH NUCLEAR PLANT, UNIT N0.-2 j

q AMENDMENT TO FACILITY OPERATING LICENSE i

83 Amendment No.

]

License No..NPF-5 1... Thel Nuclear-Regulatory Comission (the Comission) has found that:

A.

The application for amendment to the Edwin 1. Hatch Nuclear Plant, Unit 2 (the-facility) Facility Operating License No. NPF-5 filed by Georgia Power. Company, acting-for itself -Oglethorpe Power Corporation, Municipal Electric Authority of Georgia, and City of Dalton. Georgia, (the licensee) dated March 31', 1986 -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; 3

J 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 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 Comission's regulations set forth in 10 CFR

. Chapter I; 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 Comission's regulations and all applicable requirements have been satisfied.

4

. 2.

Accordingly, the license is amended by changes to the Technical Speciff-cations as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-5 is hereby amended to read as follows:

l (2)

Technical Specifications The Technical Specifications contained in Appendices A and B, at revised through Amendment No. 83, are hereby incorporated in the t

license.

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

3.

This license amendment is effective as of its date of issuance and shall be implemented within 60 days of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

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Darl S. Hood, Acting Director Project Directorate II-3 Division of Reactor Projects-I/II

Attachment:

Changes to the Technical

. Specifications Date of Issuance:

August 25, 1987 l

156 l

PD#Q-hDRP-I/II PD#II /DRP-I/II GC-Be,tpesda PD#II-3/DRP-I/II Mbuill;an'/mac LCroc er h-<,a w w. h DHood, Acting Director 8/6/87 08/ g /87 08/ 3 /87 08/(,/87

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4 ATTACHMENT TO LICENSE AMENDMENT NO. 83 l

FACILITY OPERATING LICENSE N0. NPF-5 DOCKET NO. 50-366

. Replace the following pages of the Appendix' A Technical Specifications with the enclosed pages. The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.

Remove Insert Page Page 3/4 8-1 3/4 8-1 3/4 8-2 3/4 8-2 3/4 8-3 3/4 8-3 l-3/4 8-3a 3/4 8-5 3/4 8-5 3/4-8-8 3/4 8-8 l

l 1

-3/4.8 ELECTRICAL POWER SYSTEMS.

3/4. 8.1' A.C. SOURCES A.C. SOURCES - OPERATING I

LIMITING CONDTION FOR OPERATION 1

(

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3.8.1.1 As a minimum, the following A.C. electrical power 3, areas shall) by OPERABLE:

Two physically independent circuits between the off site trans-a.

mission network and the onsite Class 1E distribution system, and b.

Three separate'and independent diesel generators, each with:

l 1.

A separate,ay tank containing a minimum of 900 gallons of fuel, l

2.

A separate' fuel storage tank containing a minimum of 32,000 gallons of fuel, and 3.

A separate f uel transfer pump.

APPLICABILITY:

CONDTIONS 1, 2, and 3.

ACTION:

With one off site circuit of the above required A.C. electrical a.-

power sources inoperable, demonstrate the OPERABILITY of the remaining off site A.C. source by perf orming Surveillance. Require-ment 4.8.1.1.1.a within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months

(

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thereaf ter, and perf orming Surveillance Requirement 4.8.1.1.2.a.4 within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . Restore at least two off site circuits to

's OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HOT SEUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the f ollowing

~

24' hours.

b.

With one diesel generator of the above required A.C. electrical power sources inoperable, demonstrate the OPERABILITY of the l

i remaining A.C. sources.by perf orming Surveillance Requirement 4.8.1.1.1.a within one hour and at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months there-af ter, and by perf orming Surveillance Requirement 4.8.1.1.2.a.4 l

within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . Restore at least three diesel generators to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-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 and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

}

a HATCH - UNIT 2 3/4 8-1 Amendment No. 83 l

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NELECTRICAL POWER SYSTEMS

( LT.MITING CONDITION FOR OPERATION (Continued)

ACTION (Continued) i With one offsite circuit and one diesel generator of the above l

c.

T required A.C. electrical power sources inoperable, demonstrate the OPERABILITY of the remaining A.C. sources by performing Surveillance Requirement 4.8.1.1.1.a within I hour and at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereaf ter, and by' performing Surveillance Requirement 4.8.1.1.2.a.4 within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months . Restore at least one of the in-I operable sources to OPERABLE status within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 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 and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

Restore the other A.C. power source

)

(offsite circuit or diesel generator set) to OPERABLE status in accordance with thearovisions of Section 3.8.1.1, Action State-ments a or b, as appropriate, from the time of initial loss.

d.

With two of the above required offsite A.C. circuits inoper-l able, demonstrate the OPERABILITY of three diesel generators by performin; Surveillance Requirement 4.8.1.1.2.a.4 within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months , unless the diesel generators are already operating; restore at least one of the inoperable offsite sources to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or be in at least HOT SHUTOOWN with the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months . With only one offsite source re-stored, restore the remaining offsite circuit to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months from the time of initial loss 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 and in s

COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

With two of the above required diesel generators inoperable, e.

l 3

demonstrate the OPERABILITY of the remaining A.C. sources by l

l performing Surveillance Requirements 4.8.1.' 1.1.a. and 4.8.1.1.2.a.4 within I hour and at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter.

Restore at least one of the inoperable diesel generators to t

OPERABLE status within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 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 and in COLD SHUTDOWN within the i

{

following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

Restore three diesel generators to OPERABLE

{

status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months from the time of initial loss 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 and in COLD SHU100WN i

within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

1

)

s i

i HATCH - UNIT 2 3/4 8-2 Amendment No. 83

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ELECTRICAL POWER SYSTEMS SURVEILLANCE REQUIRD4ENTS 4.8.1.1.1 Each of the above required independtat circuits etween the cff site transmission network and the onsite Class 1E distribution

,o cystem shall be 1

a.

Determined OPERABLE at least once per 7 days by verifying. ' t correct breaker alignments and indicated power availability, and b.

Demonstrated OPERABLE at least once per 18 months during shutdown by transferring, manually and automatically, unit power supply from the normal circuit to the alternate circuit.

i 4.8.1.1.2 Each diesel generator shall be demonstrated OPERABLE:

In accordance with the_ frequency specified in Table 4.8.1.1.2-1 s.

on a STAGGERED TEST BASTS by:

1.

Verif ying the fuel level in the day fuel tanks.

1 2.

Verifying the fuel level in the plant fuel storage tank.

.t;ying the fuel transfer pump can be started and 3e e

transfers fuel from the storage system to the day tank.

4.

Verif ying that each diesel starts f rom ambient condition by gradually loading the generator to 1710-2000 kW*,

and operating for > 60 minutes.

5.

Verifying the diesel generator is aligned to provide l

standby power to the associated emergency busses.

6.

Verifying the pressure in both diesel air start receivers l

to be > 225 psig.

b.

At least once per 184 days by verifying the diesel starts from ambient condition and accelerates to synchronous speed in 5 12 seconds,. is loaded to 2764-2825 kW* for diesel generator 2A, 2360-2425 kW* for diesel generator 1B, and 2742-2825 kW* for diese] generator 2C in,$,

J 120 seconds, and operates for > 60 minutes thereaf ter.

At least once per 92 days by verifying that a sample of diesel l

c.

fuel from the fuel storage tank, obtained in accordance with

/

ASTM-D270-65, is within the acceptable limits specified in Table 1 of ASTM D975-74 when checked for viscosity, water and sediment.

r;'

Fos.intary variations outside this band shs11 not invalidate the test.

[

HATCH - UNIT 2 3/4 8-3 Amendment No. 83

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ELECTRICAL POWER SYSTEMS'

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SURVEILLANCE RFFIIRA'46MTS (Continued) 4 Ms

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-J/'At b est onet,yer 18 months during chutdown by:

d.

.s r.Subjectingtpe'dieseltoaninspectioninaccordanceWith

,p procedures prepared in conjunction with its manuf acturer's-a

/

re, commendations for;this class of standby service.

.g

[ "2.

Verif ying that the automatic load sequence timer is OPERABLE with the interval between each load block within j

'/

+

3 10% of its design. interval.

3.

Verifying the generator capability to reject a load of

> 798 kw while maintaining voltage at 4160 1 400 volts and frequency at 60 + 2 Hz.

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1 HATCH - UNIT 2 3/4 8-3a hnendment No. 83 2

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1 ELECTRICAL POWER SYSTEMS SURVEILLANCE REQUIRD4ENTS (Continued) 9.

Verifying that the diesel generator operates for at least 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . During the first 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months of this test, the diesel generator shall be loaded to 2 2950 kW for diesel generator 2A, 2 2547 kW for diesel generator 18 and 2 2928 kW for diesel generator 2C and during the remaining 22 hours2.546296e-4 days 0.00611 hours 3.637566e-5 weeks 8.371e-6 months of this test, the diesel generator shall be loaded to 2764-2825 kW" for diesel generator 2A, 2360-2425 kW* for diesel generator IB and 2742-2825 kW* for diesel generator 2C. Within 5 minutes after completing this 24-hour test, repeat Specification 4.8.1.1.2.d.5.

10. Verif ying that the auto-connected loads to each diesel generator do not exceed the 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months rating of 3135 kw.

11.

Verifying the diesel generator's capability to:

a) Synchronize with the off site power source while the Senerator is loaded with its emergency loads upon a simulated restoration of off site power, b) Transfer its loads to the off site power source, and c) Proceed through its shutdown sequence.

12. Verif ying that with the diesel generator operating in a test mode (connected to its bus), a simulated saf ety injection signal overrides the test mode by (1) returning the diesel generator to standby operation and (2) auto-matica11y energizes the emergency loads with off site power.

13. Verifying that the fuel transfer pump transfers fuel from each fuel storage tank to the day tank of each diesel via i

I the installed cross connection lines.

At least once per 5 years by verif ying that with both air e.

start receivers pressurized to 5,225 psig and the compressors secured, the diesel generator starts at least 5 times from ambient conditions and accelerates to sychronous speed in ji12 seconds.

f.

At least once per 10 years or af ter any modifications which l

could aff ect diesel generator interdependence by starting both diesel generators simultaneously, during shutdown, and verifying that both diesel generators accelerate to synchronous speed in

E 12 seconds.

Miomentary variations outside this band shall not invalidate the test.

HATCH - UNIT 2 3/4 8-5 Amendment No. 83

. m u.. _ ;.a. a s u i 2

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TABLE 4.8.1.1.2-1 pIESEL GENERATOR TEST SCHEDULE l

Number of Failures In 1

Last'20 Valid Tests

Test Frequency 5,1 At least once per 31 days 1 2

'At least once per 7 days

.~

i i

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Criteria for determining number of f ailures and number of valid l

testa shall be in accordance with Regulatory Position C.2.e of Regulatory Guide 1.108, Revision 1 August 1977, except that only the last 20 tests are used and are determined on a per diesel basis.

I HATCH - UNIT 2 3/4 8-8 Amendment No. 83

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...

v t e Letter Sequence Other
TAC:55865, (Approved, Closed) TAC:55866, (Approved, Closed)
Initiation Request, Request, Request, Request Acceptance... Administration Meeting Questions Answers Results Approval Other: 05000366/LER-1985-005-01, :on 850329,determined That Battery Surveillance Procedure Contained Acceptance Criteria That Did Not Satisfy Tech Specs.Caused by Procedural Inadequacy.Procedure Being Revised, ML20062D710, ML20099E184, ML20099L199, ML20099L430, ML20202F737, ML20237K230, ML20237K247
MONTHYEAR1984-08-16 [Table View]

ML20237K230

Text

Attachment:

Attachment:

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