ML20237E182

Amends 214 & 195 to Licenses NPF-4 & NPF-7,respectively, Changing NAPS TS to Allow an Extended Allowed Outage Time of 14 Days for One EDG

ML20237E182
Person / Time
Site:	North Anna
Issue date:	08/26/1998
From:	Kuo P NRC (Affiliation Not Assigned)
To:
Shared Package
ML20237E184	List: ML20237E182 ML20237E187
References
NUDOCS 9808310019
Download: ML20237E182 (50)

Text

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1. 1 UNITED STATES f,

j NUCLEAR REGULATORY COMMISSION Y

f WASHINGTON, D.C. m =1 d

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4 VIRGINIA ELECTRIC AND FOWER COMPANY OLD DOMINION ELECTRIC COOPERATIVE DOCKET NO. 50-338 NORTH ANNA POWER STATION. UNIT NO.1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 214 License No. NPF-4 1.

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

A.

The application for amendment by Virginia Electric and Power Company et al., (the licensee) dated September 1,1995, as supplemented April 8,1996; April 22,1996; April 23,1996; November 18,1997; February 9,1998; March 25,1998; May 5,1998; June 25,1998, and June 29,1998, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act, j

and the rules and regulations of the Commission; i

C.

There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.

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

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Commission's regulations and all applicable requirements have been satisfied.

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i 9808310019 980826

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PDR ADOCK 05000338 l

P em L_--______

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.. ' 2.

Accordingly, the license is amended by changes to the Technical Specifications as

. indicated in the attachment to this license amendment, and paragraph 2.D.(2) of Facility Operating License No NPF-4 is hereby amended to read as follows:

(2) ' : Technical Specifications

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- The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 214, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

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l 3.

In addition, the license is amended to add paragraph 2.D.(3)f. to the Facility Operating j

License No. NPF-4 as follows:

J f.

The Additional Conditions contained in Appendix C, as revised through Amendment

. No. 214, are hereby incorporated into this license. Virginia Electric and Power Company shall operate the facility in accordance with the Additional Conditions.

' 4. '

This license amendment is effective as of its date of issuance and shall be implemented

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.within 30 days.

FOR THE NUCLEAR REGULATORY COMMISSION

[bbv A

P. T. Kuo, Acting Directorj Project Directorate 11-1 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation j

l Attachments:

1. Page 5 of License No. NPF-4

2. Appendix C to License No. NPF-4

3. Changes to the Technical Specifications i

Date ofissuance:

August 26, 1998 o

ATTACHMENT TO LICENSE AMENDMENT NO. 214 TO FACILITY OPERATING LICENSE NO. NPF-4 DOCKET NO. 50-338 Replace the following pages of the Operating License with the enclosed pages. The revised pages are identified by Amendment number and contain vertical lines indicating the areas of change.

Remove Paaes insert Paaes 5

5 Appendix C Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages as indicated. The revised pages are identified by amendment number and contain verticallines indicating the areas of change. Overleaf pages B 3/4 0-1 and B 3/41-1 are included for document completeness.

Remove Paats insert Paaes 1 1-3 3/4 8-1 3/4 8-1 3/4 8-2 3/4 8-2 3/4 8-2a 3/4 8-2a 3/4 8-3 3/4 8-3 3/4 8-3a 3/4 8 3a 3/4 8-3b 3/4 8-3b 3/4 8-3c 3/4 8-3c

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3/4 8-4 3/4 8-4 3/4 84c 3/4 84c j

3/4 84d 3/4 84d 1

3/4 6-5 3/4 8-5 I

B 3/4 0-2 B 3/4 0-2 8 3/4 1-2 B 3/4 1-2 B 3/4 8-1 B 3/4 8-1 B 3/4 8-2 8 3/4 8-2

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6-13c 6-13c l

6-14 6-14 1

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. f. The Additional Conditions contained in Appendix C, as revised through Amendment No. 214 ', are hereby incorporated into this license. Virginia Electric and Power Company shall oparate the facility in accordance with the Additional Conditions.

J. The Virginia Electric and Power Company shall modify or replace the presently installed Barton Models No. 763 and No. 764 Lot 1 Transmitters used in safety-related circuits inside containment with transmitters that have been demonstrated to provide a greater tolerance to harsh environments.

The modifications or replacement of these transmitters shall be completed as soon as practicable but not later than June 30,1982.

o. The provisions of Specification 4.0.4 are not applicable to the performance of surveillance activities associated witn diesel generator battery Technical Specification 4.8.1.1.3.d until the completion of the initial surveillance interval associated with that specification.

r. The Virginia Electric and Power Company shall perform a secondary water chemistry monitoring program to inhibit steam generator tube degradation.

This program shallinclude:

1. Identification of a sampling schedule for the critical parameters and control points for these parameters;

2. Identification of the procedures used to quantify parameters that are critical to control points; I

3. Identification of process sampling points;

4. Procedures for the recording and management of data;

5. Procedures defining corrective actions for off control point chemistry conditions; and j

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i Amendment No. -3+r 214 1

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APPENDIX C ADDITIONAL CONDITION FACILITY OPERATING LICENSE NO. NPF-4 Amendment implementation Number Additional Condition:

Date 214 The licensee shall implement a procedure that will Prior to prohibit entry into an extended Emergency Diesel impim.antation of Generator Outage Time (14 days), for scheduled Amendment maintenance purposes, if severe weather conditions No. 214 are expected, as described in the licensee's application dated June 25,1998, and evaluated in the staff's Safety Evaluation dated August 26, 1998.

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.__________-______-___A

4 1.0 DEFINITIONS (Continued)

FNGINFFRED S AFFTY FF ATIIRE RFSPONSF TIMF 1.12 The ENGINEERED S AFETY FEATURE RESPONSE TIME shall be that time interval from when the monitored parameter exceeds its ESF actuation setpoint at the channel sensor until the ESF equipment is capable of performing its safety function (i.e., the valves travel to their required positions, pump discharge pressures reach their required values, etc.). Times shall include emergency diesel generator starting and sequence loading delays where applicable.

l FRFOUENCY NOTATION 1.13 The FREQUENCY NOTATION specified for the performance of Surveillance Requirements shall correspond to the intervals defined in Table 1.2.

F1TI 1 Y WITHDR A%W l.13a The control bank FULLY WITHDRAWN position shall be within the interval of 225 to 229 steps withdrawn, inclusive. Definition of the FULLY WITHDRAWN position for each specific cycle shall be documented in the rod insertion limit operator curve.

GASFOUS R ADWASTE TREATMENT SYSTFM 1.14 A GASEOUS RADWASTE TREATMENT SYSTEM is the system designed and installed to reduce radioactive gaseous effluents by collecting primary coolant system offgases from the primary system and providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment. The system is composed of the waste gas decay tanks, regenerative heat exchanger, waste gas charcoal filters, process vent blowers, waste gas surge tanks and waste gas diaphragm compressor.

IDENTIFIFD I_F AK AGF 1.15 IDENTIFIED LEAKAGE shall be:

Leakage (except CONTROLLED LEAKAGE)into closed systems, such as pump a.

seal or valve packing leaks that are captured and conducted to a sump or collecting tank, or b.

Leakage into the containment atmosphere from sources that are both specifically located and known either not to interfere with the operation ofleakage detection systems or not to be PRESSURE BOUNDARY LEAKAGE, or c.

Reactor coolant system leakage through a steam generator to the secondary system.

MEMBER (S) OF THE PITRI IC 1.16 MEMBER (S) OF THE PUBLIC shall include all individuals who by virtue of their occupational status have no formal association with the plant. This category shall include non-employees of the licensee who are permitted to use portions of the site for recreational, occupational, or other purposes not associated with plant functions. This category shall no1 include non-employees such as vending machine servicemen or postmen who, as part of their formaljob function, occasionally enter an area that is controlled by the licensee for purposes of protection of individuals from exposure to radiation and radioactive materials.

NORTH ANNA - UNIT 1 1-3 Amendment No. !6, A9, ! A6, ! A9, 214 i

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314,H FI FCTRICAI. POWER SYSTEMS 3/4 1 1 A.C. SOURCFS OPERATING LIMITING CONDITION FOR OPERATION 3.8.1.1 As a minimum, the following A.C. electrical power sources shall be OPERABLE:

a.

Two physically independent circuits between the offsite transmission network and the onsite Class IE distribution system, and b.

Two separate and independent emergency diesel generators (EDGs):

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1. Each with a separate day tank containing a minimum of 450 gallons of fuel, and

2. A fuel storage system consisting of two underground storage tanks each containing a minimum of 45,000 gallons of fuel (This is a shared system with Unit 2), and

3. A separate fuel transfer system.

APPI TCABTI TTY-MODES 1,2,3 and 4 ACTION-With one offsite circuit of 3.8.1.1.a inoperable, demonstrate the OPERABILITY of a.

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 <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> thereafter Restore the offsite circuit to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

b.

(Risk Informed) With one EDG of 3.8.1.1.b inoperable, demonstrate the l

OPERABILITY of the offsite A.C. power sources by performing Surveillance

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Requirement 4.8.1.1.1.a within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> thereafter. If the

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EDG is inoperable due to any cause other than an inoperable support system, an l

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independently testable component, or preplanned preventive maintenance or testing, demonstrate the OPERABILITY of the remaining OPERABLE EDG by i

performing Surveillance Requirement 4.8.1.1.2.a.4 within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> *, unless the absence of any potential common mode failure for the remaining EDG is demonstrated. Restore the EDG to OPERABLE status within 14 days if the AAC DG and the opposite unit's EDGs are OPERABLE or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />. In addition:

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This action is required to be completed regardless of when the inoperable EDG is restored to OPERABIL1TY.

j NORTH ANNA - UNIT 1 3/4 8 1 Amendment No. 83,128, ! S1, 303,214 I

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4 FI FFTRICAI POWER SVSTEMR LIMITING CONDITION FOR OPERATION ACTION- (Cnntimiern

1. If one cr more of the three diesel generators (i.e., AAC DG or opposite unit's EDGs) required for entry into the 14 day action statement is(are) inoperable at the start of the 14 day action statement, restore the diesel generator (s) to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the next following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

2. If one or more of the three diesel generators (i.e., AAC DG or opposite unit's EDGs) required for entry into the 14 day action statement become(s) inoperable

- during the 14 day action statement, restore the diesel generator (s) to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the next following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

With one offsite circuit and one EDG inoperable, demonstrate the OPERABILITY c.

of the remaining A.C. sources by performing Surveillance Requirement 4.8.1.1.1.a within one hour and at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> thereafter; and if the EDG became inoperable due to any cause other than an inoperable support system, an independently testable component, or preplanned preventative maintenance or testing, demonstrate the OPERABILITY of the remaining OPERABLE EDG by performing Surveillance Requirement 4.8.1.1.2.a.4 within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> *, unless the absence of any potential common mode failure for the remaining EDG is l

demonstrated. Restore one of the inoperable sources to OPERABLE status within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />. Restore the other A.C. power source (offsite circuit or EDG) to OPERABLE status in accordance with the provisions of l

Section 3.8.1.1 Action Statement a or b, as appropriate with the time requirement of that Action Statement based on the time ofinitial loss of the remaining inoperable A.C. power source.

d.

With two of the required offsite A.C. circuits inoperable, restore one of the inoperable offsite sources to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. Following restoration of one offsite source, follow Action Statement a with the time requirement of that Action Statement based on the time ofinitial loss of the remaining inoperable offsite A.C.

circuit.

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This action is required to be completed regardless of when the inoperable EDG is restored to OPERABILITY.

NORTH ANNA - UNIT 1 3/48-2 Amendment No. 83, !S1,214 l

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e FI FCTRICAI POWER SYSTFMR LIMITING CONDITION FOR OPERATION ACTION- (rnntinuedh With two of the above required EDGs inoperable, demonstrate the OPERABILITY e.

of two offsite A.C. circuits by performing Surveillance Requirement 4.8.1.1.1.a within one hour and at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> thereafter; restore one of the inoperable EDGs to OPERABLE status within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />. Following restoration of one EDG, fcllow Action Statement b with the time requirement of that Action Statement based on the time ofinitialloss of the remaining inoperable EDG.

f.

With one underground fuel oil storage tank of 3.8.1.1.b.2 inoperable for the performance of Surveillance Requirement 4.8.1.1.4 or for tank repairs:

1. Verify 45,000 gallons of fuel is available in the operable underground fuel oil storage tank at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />,

2. Verify a minimum of 100,000 gallons of fuel is maintained in the above ground I

main fuel oil storage tank at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />,

3. Verify an available source of fuel oil and transportation to supply 50,000 l

gallons of fuel in less than a 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> period, and

4. Restore the storage tank to OPERABLE status within 7 days or place both Units in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

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NORTH ANNA - UNIT 1 3/4 8-2a Amendment No. 438, 214 t.

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l FI FCTRICAL POWER SYSTEMS l

SURVEILLANCE REQUIREMENTS 4.8.1.1.1 Each of the above required physically independent circuits between the offsite transmission network and the onsite Class IE distribution system shall be:

l 1

Determined OPERABLE at least once per 7 days by verifying correct breaker l

a.

1 alignment indicating power availability.

I b.

Demonstrated OPERABLE at least once per 18 months during shutdown by i

manually transferring the onsite Class IE power supply from the normal circuit to l

the altemate circuit.

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1 4.8.1.1.2 Each emergency diesel generator (EDG) shall be demonstrated OPERABLE:

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In accordance with the frequency specified in Table 4.8.2 on a STAGGERED a.

TEST BASIS by:

1. Verifying the fuellevelin the day tank.

2. Verifying the fuel level in the fuel storage tank.

3. Verifying the fuel transfer pump can be started and transfers fuel from the storage system to the day tank.

4. Verifying the EDG can start ** and gradually accelerate to synchronous speed l

(900 rpm) with generator voltage and frequency at 4160 420 volts and 60 1.2 Hz. Subsequently, verifying the generator is synchronized, gradually i

loaded *

• to an indicated 2500-2600 kw* ** and operates for at least 60 minutes.

5. Verifying the EDG is aligned to provide standby power to the associated l

emergency busses, b.

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

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This test shall be conducted in accordance with the manufacturer's recommendations I

regarding engine prelube and warmup procedures, and as applicable regarding loading j

recommendations.

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l This band is meant as guidance to avoid toutine overloading of the engine. Loads in excess i

of this band for special testing under direct monitoring of the manufacturer or momentary variations due to changing bus loads shall not invalidate the test.

i NORTH ANNA - UNIT 1 3/48-3 Amendment No. 84,214 t

FI FCTRICAI. POWER SYSTEMR l

SURVEILLANCE REQUIREMENTS 4.8.1.1.2 (Continued) c.

At least once per 184 days, the EDG shall be started ** and accelerated to at least j

900 rpm in less than or equal to 10 seconds. The generato voltage and frequency shall be 4160 i 420 volts and 60i 1.2 Hz within 10 seconds after the stan signal.

The EDG shall be manually synchronized to its appropriate emergency bus, l

gradually loaded ** to an indicated 2500 to 2600 kw'**, and operated for at least 60 minutes. The EDG shall be staned for this test by using one of the following l

signals on a rotating test basis:

a)

Simulated loss of offsite power by itself.

b)

Simulated loss of offsite power in conjunction with an ESF actuation test signal.

c)

An ESF actuation test signal by itself.

This test, ifit is performed so it coincides with the testing required by Surveillance Requirement 4.8.1.1.2.a.4, may also serve to concurrently meet those requirements as well, d.

At least once per 18 months during shutdown by:

1.

Verifying that, on rejection of a load of greater than or equal to 610 kw, the l

voltage and frequency are maintained with 4160 420 volts and 60 1.2 Hz.

2.

Verifying that the load sequencing timers are OPERABLE with times l

within the tolerances shown in Table 4.8-1.

This test shall be conducted in accordance with the manufacturer's recommendations regarding engine prelube and warmup procedures, and as applicable regarding loading recommendations.

This band is meant as guidance to avoid routine overloading of the engine. Loads in excess of this band for special testing under direct monitoring of the manufacturer or momentary l

variations due to changing bus loads shall not invalidate the test.

l NORTH ANNA - UNIT 1 3/4 8-3a Amendment No. 83, !S1, 214

FI FFTRICAI POWER SYSTEMS SURVEILLANCE REQUIREMENTS 4.8.1.1.2 (Continued) 3.

Simulating a loss of offsite power by itself, and:

l Verifying de-energization of the emergency busses and load shedding a.

from the emergency busses.

b. Verifying the EDG starts ** on the auto-start signal, energizes the l

emergency busses with permanently connected loads within 10 seconds, energizes the auto-connected shutdown loads through the sequencing timers and operates for greater than or equal to 5 minutes while its generator is loaded with the shutdown loads. After energization of these loads, the steady state voltage and frequency shall be maintained at 4160 420 volts and 60 1.2 Hz.

4.

Verifying that on an ESF actuation test signal (without loss of offsite power) the EDG starts *

• on the auto-start signal and operates on standby for greater than or equal to 5 minutes.

5.

Simulating a loss of offsite power in conjunction with an ESF actuation test l

signal, and Verifying de-energization of the emergency busses and load shedding a.

from the emergency busses.

b. Verifying the EDG starts ** on the auto-start signal, energizes the l

emergency busses with permanently connected loads within 10 seconds, j

energizes the auto-connected emergency (accident) loads through the

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sequencing timers and operates for greater than or equal to 5 minutes

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and maintains the steady state voltage and frequency at 4160i420 volts l

and 60 1.2 Hz.

Verifying that all EDG trips, except engine overspeed, generator l

c.

differential and breaker overcurrent are automatically bypassed upon loss of voltage on the emergency bus and/or a safety injection actuation signal.

6.

Verifying the EDG operates" for at least 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. During the first 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> of this test, the EDG shall be loaded to an indicated target value of 2950 kw (between 2900-3000 kw)*** and during the remaining 22 hours2.546296e-4 days <br />0.00611 hours <br />3.637566e-5 weeks <br />8.371e-6 months <br /> of this test, the EDG shall be loaded to an indicated 2500-2600 kw"*.

This test shall be conducted in accordance with the manufacturer's recommendations regarding engine prelube and warmup pn>cedures, and as applicable regarding loading recommendations.

g This band is meant as guidance to avoid routine overloading of the engine. Loads in excess of this band for special testing under direct monitoring of the manufacturer or momentary variations due to changing bus loads shall not invalidate the test.

NORTH ANNA - UNIT 1 3/4 8-3b Amendment No. E, 214 I

A FI FCTRICAI POWER SYSTEMR SURVEILLANCE REQUIREMENTS 4.8.1.1.2 (Continued).

7.

Verifying that the auto-connected loads to each EDO do not exceed the l

2000 hour0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br /> rating of 3000 kw.

8.

Verifying the EDG > capability to:

a) Synchro ic with the otidte power source while the EDG is loaded with its emergency loads upon a simulated restoration of offsite power, b) Transfer its loads to the offsite power source, and c) Proceed through its shutdown sequence.

9.

Verifying that the following EDG lockout features prevent EDG starting

.l only when required:

a) Remote Local Selection Switch b) Emergency Stop Switch 10.

Verifying the EDG's hot restart capability by:

a) Operating the EDG** loaded to an indicated 2500 to 2600 kw*** for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or until operating temperatures have stabilized, and b) Within 5 minutes of shutdown verify the EDG can be started ** and l

accelerated to at least 900 rpm in less than or equal to 10 seconds. The generator voltage and frequency shall be 4160 420 volts and 60 1.2 Hz within 10 seconds after the start signal.

e.

At least once per 10 years or after any modifications which could affect EDG interdependent by starting ** both EDGs simultaneously, during shutdown, and verifying that both EDGs accelerate to at least 900 rpm in less than or equal to 10 seconds.

f.

At least once per 24 months during any mode of operation, by subjecting each EDG

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to a preventive maintenance inspection in accordance with maintenance procedures I

l appropriate for diesels used for this class of standby service.

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This test shall be conducted in accordance with the manufacturer's recommendations regarding engine prelube and warmup procedures, and as applicable regarding loading recommendations.

This band is meant as guidance to avoid routine overloading of the engine. Loads in excess of this band for special testing under direct monitoring of the manufacturer or momentary variations due to changing bus loads shall not invalidate the test.

NORTH ANNA - UNIT 1 3/4 8-3c Amendment No. Sh 115, !M, 214 i

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4 FI FFTRICAI. POWER SYSTEMS SURVEILLANCE REQUIREMENTS 4.8.1.1.3 Each emergency diesel generator 125-volt battery bank and charger shall be l

demonstrated OPERABLE:

. At least once per 7 days by verifying that:

a.

1.

The parameters in Table 4.8-3 meet Category A limits and 2.

The total ba:tery terminal voltage is greater than or equal to 129 volts on a float charge, b.

At least once per 92 days and within 7 days after a battery discharge where the battery terminal voltage decreased below 110 volts or battery overcharge above 150 volts, by verifying that:

1.

The parameters in Table 4.8-3 meet Category B limits and 2.

There is no visible corrosion at either terminals or connectors, or the connection resistance of these items is less than 150 x 10 to the minus 6 ohms.

At least once per 18 months, by verifying that:

c.

1.

The cells, cell plates and battery racks show no visual indication of physical damage or r.bnormal deterioration.

2.

The cell-to-cell and terminal connections are clean, tight and coated with anti-corrosion material.

3.

The resistance of each cell-to-cell and terminal connection is less than or equal to 150 x 10-6 ohms.

4.

The battery charger will supply at least 10 amperes at 125 volts for at least 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

d.

At least once per 60 months, during shutdown, by verifying that the battery capacity is at least 80% of the manufacturer's rating when subjected to a performance discharge test.

At least once per 18 months, during shutdown, perform a performance discharge e.

test of battery capacity if the battery shows signs of degradation or has reached 85%

ofits service life expected for the application. Degradation is indicated when the battery capacity drops more than 10% of rated capacity from its average from previous performance discharge tests, or is below 90% of the manufacturer's rating.

NORTH. ANNA - UNIT 1 3/4 8-4 Amendment No. 83rW, 214

FI FCTRICAL POWER SYSTEMS Table 4L2 EMFRGENCY DIFSFT GENERATOR TFST SCHFDUI F l

Number of Failures in Number of Failures in T.nct 20 Valid Tects*

I nct 100 Valid Tectc*

' Test Frequency 51 54 Once per 31 (Nys 2 2**

25 Once per 7 days 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, but determined on a per emergency diesel generator basis.

l For the purposes of determining required test frequency, the previous test failure count may be reduced to zero if a complete diesel overhaul to like-new conditions is completed, provided that the overhaul including appropriate post-maintenance operation and testing,is specifically approved by the manufacturer and if acceptable reliability has been demonstrated. The reliability criterion shall be the successful completion of 14 consecutive tests in a single series. Ten of these tests shall be in accordance with Surveillance Requirement 4.8.1.1.2.a.4; four tests, in accordance with Surveillance Requirement 4.8.1.1.2.c. If this criterion is not satisfied during the first series of tests, any alternate criterion to be used to transvalue the failure count to zero requires NRC approval.

l The associated test frequency shall be maintained until seven consecutive failure free demands have been performed and the number of failures in the last 20 salid demands has been reduced to one.

l l

l-NORTH ANNA - UNIT 1 3/4 8-4c Amendment No. 83, 214 l

i EI ECTRICAI POWER SYSTEMS SURVEILLANCE REQUIREMENTS 4.8.1.1.4 For each underground EDG fuel oil storage tank perform the following at least once per l

10 years:

1.

Drain each fuel oil storage tank 2.

Remove sediment from each fuel oil storage tank 3.

Inspect each fuel oil storage tank for integrity 4.

Clean each fuel oil storage tank.

)

i i

l NORTH ANNA - UNIT 1 3/4 8-4d Amendment No. 438, 214

O ELECTRICAI. POWER SYSTEMS SHilTDOWN LIMITING CONDITION FOR OPERATION 3.8.1.2 As a minimum, one of the following trains of A.C. electrical power sources shall be OPERABLE:

One circuit between the offsite transmission network and the onsite Class 1E a.

distribution system, and b.

One emergency diesel generator with:

[

1. A day tank containing a minimum volume of 450 gallons of fuel;

2. A fuel storage system consisting of two underground storage tanks each containing a minimum volume of 45,000 gallons of fuel (This is a shared system with Unit 2), and

3. A fuel transfer system.

APPI ICAllil TTY:

a.

Modes 5 and 6 b.

During movement ofirradiated fuel assemblies or loads over irradiated fuel assemblies when no fuel assemblies are in the reactor vessel.

ACTION:

With less than the ' bove minimum required A.C. electrical power sources a.

a OPERABLE, immediately suspend all operations involving CORE ALTERATIONS, positive reactivity changes, movement ofirradiated fuel assemblies, and movement ofloads over irradiated fuel assemblies until the minimum required A.C. electrical power sources are restored to OPERABLE status.

b.

With one underground fuel oil storage tank of 3.8.1.2.b.2 inoperable for the performance of Surveillance Requirement 4.8.1.1.4 or for tank repairs:

1. Verify 45,000 gallons of fuelis available in the operable underground fuel oil storage tank at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />,

2. Verify a minimum of 100,000 gallons of fuel oil is maintained in the above ground main fuel oil storage tank at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />,

3. Verify an available source of fuel oil and transportation to supply 50,000 j

gallons of fuel in less than a 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> period, and l

4. Restore the storage tank to OPERABLE status within 7 days or place both Units l

in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and COLD SHUTDOWN l

within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />, and perform ACTION a. above.

I I

SURVEILLANCE REQUIREMENTS 1

l i

4.8.1.2 The above required A.C. electrical power sources shall be demonstrated OPERABLE by the performance of each of the Surveillance Requirements of 4.8.1.1.1,4.8.1.1.2,4.8.1.1.3, and 4.8.1.1.4.

I NORTH ANNA - UNIT 1 3/48-5 Amendment No. ! !,83,128,156

(

M3, 214 l

l

.___________A

o o

e-3/4.0 APPLICABILITY BASES The specifications of this section provide the general requirements applicable to each of the Limiting Conditions for Operation and Surveillance Requirements within Section 3/4.

3.0.1 This specification defines the applicability of each specifica-tion in terms of defined OPERATIONAL M0PC, or other specified conditions and is provided to delineate specifically when each specification is applicable.

3.0.2 This specification defines those conditions necessary to constitute compliance with the terms of an individual Limiting Condition.for Operation and associated ACTION requirement.

3.0.3 This specification delineates the ACTION to be taken for circum-stances not directly provided for in the ACTION statements and whose occurrence would violate the intent of the specification.

For example, Specification 3.5.1 calls for each Reactor Coolant System accumulator to be OPERABLE and provides explicit ACTION requirements when one accumulator is inoperable.

Under the terms of Specification 3.0.3, if more than one accumulator is inoper-able, within one hour measures must be initiated to place the unit in at least H0T STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in at least HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. As a further example, Specification 3.6.2.1 requires two Containment Quench Spray Systems to be OPERABLE and provides explicit ACTION requirements if one spray system is inoperable.

Under the terms of Specification 3.0.3, if both of the required Containment Quench Spray Systems are inoperable, within one hour measures must be initiated to place the unit in at least HOT STANDBY dithin 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, in at least HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and in at least COLD SHUTDOWN in the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

3.0.4 This specification provides that entry into an OPERATIONAL MODE cr other specified applicability condition must be made with (a) the full comple-ment of required systems, equipment or components OPERABLE and (b) all other parameters as specified in the Limiting Conditions for Operation being met without regard for allowable deviations and out of service provisions contained 4

in the ACTION statements.

l The intent of this provision is to insure that facility operation is not initiated with either required equipment or systems inoperable or other specified limits being exceeded.

l l

Exceptions to this provision have been provided for a limited number of l

specifications when startup with inoperable equipment would not affect plant i

safety. These exceptions are stated in the ACTION statements of the appropriate

)

specifications.

I NORTH ANNA - UNIT 1 B 3/4 0-1 Amendment No. JS, 62

1 4

APPI ICAMI TTY BASES 3.0.5 This specification delineates what additional conditions must be satisfied to permit operation to continue, consistent with the ACTION statements for power sources, when a normal or emergency power source is not OPERABLE. It specifically prohibits operation when one division is inoperable because its normal or emergency power source is inoperable and a system, subsystem, train, component or device in another division is inoperable for another reason.

The provisions of this specification permit the ACTION statements associated with individual systems, subsystems, trains, components, or devices to be consistent with the ACTION statements of the associated electrical power source. It allows operation to be governed by the time limits of the ACTION statement associated with the Limiting Condition for Operation for the j

normal or emergency power source, not the individual ACTION statements for each system, subsystem, train, component or device that is determined to be inoperable solely because of the inoperability ofits normal or emergency power source.

For example, Specification 3.8.1.1 requires in part that two emergency diesel generators be OPERABLE. The ACTION statement provides for an out-of-service time when one emergency l

diesel generator is not OPERABLE. If the definition of OPERABLE were applied without consideration of Specification 3.0.5, all systems, subsystems, trains, components and devices supplied oy the inoperable emergency power source would also be inoperable. This would dictate invoking the applicable ACTION statements for each of the applicable Limiting Conditions for Operation. However, the provisions of Specification 3.0.5 permit the time limits for continued operation to be consistent with the ACTION statement for the inoperable emergency diesel generator instead, provided the other specified conditions are satisfied. In this case, this would mean that the corresponding normal power source must be OPERABLE, and all redundant I

systems, subsystems, trains, components, and devices must be OPERABLE, or otherwise satisfy I

Specification 3.0.5 (i.e., be capable of performing their design function and have at least one normal or one emergency power source OPERABLE). If they are not satisfied, shutdown is required % accordance with this specification.

As a further example, Specification 3.8.1.1 requires in part that two physically independent circuits between the offsite transmission network and the onsite Class IE distribution system be OPERABLE. The ACTION statement provides a 24-hour out-of-service time when both required offsite circuits are not OPERABLE. If the definition of OPERABLE were applied without consideration of Specification 3.0.5, all systems, subsystems, trains, components and devices supplied by the inoperable normal power source, both of the offsite circuits, would also be inoperable. This would dictate invoking the applicable L

f.

NORTH ANNA - UNIT I B 3/4 0-2

. Amendment No. 49, 214 I

I

l I.

3/4.1 REACTIVITY CONTROL SYSTEMS j

1 BASES I

3/4.1.1 BORATION CONTROL 3/4.1.1.1 and 3/4.1.1.2 SHUTDOWN MARGIN A sufficient SHUTDOWN MARGIN ensures that 1) the reactor can be made subcritical from 'all operating conditions, 2) the reactivity transients associated with postulated accident conditions are controllable within acceptable limbs, and 3) the reactor will be maintained sufficiently subcritical to preclude inadvertent criticality in the shutdown condition.

SHUTDOWN MARGIN requirements vary throughout core life as a function of fuel depletion, RCS boron concentration, and RCS Tavg. The most restrictive condition occurs at EOL, with Tavg at no load operating temperature, and is associated with a postulated steam line break accident and resulting uncontrolled RCS cooldown. In the analysis of this accident, a minimum SHUTDOWN MARGIN of 1.77% Ak/k is initially required to control the reactMty transient. Accordingly, the SHUTDOWN MARGIN requirement is based upon this limiting condition and is consistent with FSAR safety analysis assumptions. With Tavg

< 200'F, the reactivity transients resulting from a postulated staam line break cooldown are minimal. A 1.77% Ak/k shutdown margin provides adequate protection for the boron dilution accident.

3/4.1.1.3 BORON DILUTION A minimum flow rate of at least 3000 GPM provides adequate mixing, prevents stratification and ensures that reactivity changes will be gradual during boron concentration reductions in the Reactor Coolant System. A flow rate of at least 3000 GPM will circulate the Reactor Coolant System volume in approximately 30 minutes. The reactivity change rate associated with boron reductions will therefore be within the capability for operator recognition an.d control.

3/4.1.1.4 MODERATOR TEMPERATURE COEFFICIENT (MTC) l The limitations on MTC are provided to ensure that the value of this coefficient remains within the limiting conditions assumed for this parameter in the FSAR accident and transient analyses.

The MTC values of this specification are applicable to a specific set of plant operations; accordingly, verification of MTC values at NORTH ANNA UNIT 1 B 3/4 1-1 Amendment No.166, 1

l l

l

(

a 3/L],

RFACTIVITY CONTROI SYSTEMS BASES 3/4 1.1.4 MODER ATOR TEMPER ATURE COEFFICIENT (MTC) (continued) conditions other than those explicitly stated will require extrapolation to those conditions in order to permit an accurate comparison.

The most negative MTC value was obtained by incrementally correcting the MTC used in the FSAR analyses to nominal operating conditions. These corrections involved adding the incremental change in the MTC associated with a core condition of Bank D inserted to an all rods withdrawn condition and an incremental change in MTC to account for measurement uncertainty at RATED THERMAL POWER conditions. These corrections result in the End of Cycle (EOC)

MTC limit. The 300 ppm surveillance limit MTC value represents a conservative value (with corrections for burnup and soluble boron) at a core condition of 300 ppm equilibrium boron concentration and is obtained by making these corrections to the EOC MTC limit.

Once the equilibrium boron concentration falls below about 60 ppm, dilution operations take an extended amount of time and reliable MTC measurements become more difficult to obtain due to the potential for fluctuating core conditions over the test interval. For this reason, MTC measurements may be suspended provided the measured MTC value at an equilibrium full power boron concentration s 60 ppm is less negative than the 60 ppm surveillance limit. The difference between this value and the EOC-MTC limit conservatively bounds the maximum credible change in MTC between the 60 ppm equilibrium boron concentration (all rods withdrawn, RATED THERMAL POWER conditions) and the licensed end-of-cycle, including the effect of boron concentration, burnup, and end-of-cycle coastdown.

The surveillance requirements for measurement of the MTC at the beginning and near the end of each fuel cycle are adequate to confirm that the MTC remains within its limits since this coefficient changes slowly due principally to the reduction in RCS boron concentration associated with fuel burnup.

3/4 1 1.5 MINIMIIM TEMPER ATifRF FOR CRITICAI.ITY This specification ensures that the reactor will not be made critical with the Reactor Coolant System average temperature less than 541*F. This limitation is required to ensure 1) the moderator temperature coefficient is within its analyzed temperature range,2) the protective instrumentation is within its normal operating range, and 3) the P-12 interlock is above its setpoint, and 4) compliance with Appendix G to 10 CFR Part 50 (see Bases 3/4.4.9).

l l

3/LL2 BORATION SYSTEMS The boron injection system ensures that negative reactivity control is available during each mode of facility operation. The components required to perform this function include 1) borated water sources,2) charging pumps,3) separate flow paths,4) boric acid transfer pumps,5) associated heat tracing systems, and 6) an emergency power supply from OPERABLE emergency l

diesel generators.

NORTH ANNA - UNIT 1 B 3/41-2 Amendment No. '5, ! !2, ! !?, 214

446, l

l E_-_----_-------------

1

3/fl FI FCTRICAL POWER RYSTEMR BASES-3/4 81 and 3/4 R 2 A.C. and D.C. POWER SOURCER AND DISTRIBUTION The OPERABILITY of the A.C. and D.C. power sources and associated distribution systems during operation ensures that sufficient power will be available to supply the safety related equipment required for 1) the safe shutdown of the facility and 2) the mitigation and control of accident conditions within the facility. The minimum specified independent and redundant A.C.

and D.C. powei sources and distribution systems satisfy the requirements of General Design Criteria 17 of Appendix "A"'to 10 CFR 50.

For each EDO, the fuel oil transfer system shall be capable of automatically transferring fuel oil to the associated EDG day tank in sufficient quantities to maintain adequate day tank level to support fullload operation of the EDG.

The ACTION requirements specified for the levels of degradation of the power sources provide restriction upon continued facility operation commensurate with the level of degradation.

The OPERABILITY of the power sources are consistent with the initial condition assumptions of the accident analyses and are based upon maintaining at least one of each of the onsite A.C. and D.C. power sources and meiated distribution systems OPERABLE during accident conditions coincidet with an assumei.oss of offsite power and single failure of the other onsite A.C. source.

Entering the 14 day EDG action statement during power operation has been shown to result in a small increase in the core damage frequency, provided the Alternate A.C. diesel generator (AAC DG)is OPERABLE and the opposite unit's EDGs are both OPERABLE. A Configuration Risk Management Program (CRMP) defined in Administrative Control Section 6.8.4.g is implemented to evaluate risk associated with the EDG outage. The EDG and AAC DG annual unavailability is limited by the Maintenance Rule Program.

When one or more of the diesel generators (i.e., AAC DG or opposite unit's EDGs) required to enter the 14 day action statement is inoperable or becomes inoperable during the L

fourteen day action statement of the affected EDG, a 72 hocr action statement is entered. If the three diesel generators (i.e., AAC DG or the opposite unit's EDGs) required to support entry into the fourteen day action statement are restored to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, the remainder of the 14 day action statement can be used. Restoring the affected EDG to service removes the conditional OPERABILITY requirements for the AAC DG and opposite unit's EDGs.

t NORTH ANNA - UNIT I B 3/4 8 Amendment No. 33,9'?, ! 56,203, 214

3bLE FI FrTRICAI POWER SYSTEMR BASES 3/4 81 and 3/4 8 '2 A C and D C POWER SOURCFR AND DISTRTRUTION (Continued)

The operability requirements for the AAC DG are specified in the Technical Requirements Manual. In addition, to be considered OPERABLE to support the founeen day action statement the AAC DG must be capable of providing power to the affected bus (i.e., connectable to the bus with the associated breakers and control power available). If the AAC DG becomes inoperable during the 14 day action statement, the OPERABILITY of the remaining EDGs does not need to be demonstrated since the AAC DG was designed and purchased according to specifications which-adequately ensure that common cause failure is not likely.

i The ACTION requirements specified in Modes 5 and 6 address the condition where sufficient power is unavailable to recover from postulated events (i.e., fuel handling accident).

Implementation of the ACTION requirements shall not preclude completion of actions to establish a safe conservative plant condition. Completion of the requirements will prevent the occurrence of postulated events for which mitigating actions would be required.

The OPERABILITY of the minimum specified A.C. and D.C. power sources and associated distribution systems during shutdown and refueling ensures that 1) the facility can be maintained in the shutdown or refueling condition for extended time periods,2) sufficient instrumentation and control capability is available for monitoring and maintaining the unit status, and 3) sufficient power is available for systems necessary to recover from postulated events in these MODES, e.g., the control room emergency ventilation system fans during a fuel handling accident.

The Surveillance Requirements for demonstrating the OPERABILITY of the diesel generators are in accordance with the recommendations of Regulatory Guide 1.9 " Selection of Diesel Generator Set Capacity for Standby Power Supplies," March 10,1971, and 1.108 " Periodic Testing of Diesel Generator Units Used as Onsite Electric Power Systems at Nuclear Power Plants" i

Revision 1. August 1977, as modified by Amendment No. 83 issued August 22,1986.

The Surveillance Requirements for demonstrating the OPERABILITY of the Emergency Diesel Generator batteries and the Station batteries are based on the recommendations of l

L Regulatory Guide 1.129," Maintenance, Testing and Replacement of Large lead Storage Batteries for Nuclear Power Plants," February 1978, and IEEE Std. 450-1980, "IEEE Recommended Practice for Maintenance, Testing and Replacement of Large I. cad Storage Batteries for Generating Stations and Substations," as modified by Amendment No. 97 issued March 25,1988.

NORTH ANNA - UNIT i B 3/4 8-2 Amendment No. 303,214

ADMINISTRATIVE CONTROLS 8)

Limitations on the annual and quarterly air doses resulting from noble gases released in gaseous effluents from each unit to areas beyond the SITE BOUNDARY conforming to Appendix I to 10 CFR Part 50,

, 9) ' Limitations on the annual and quarterly doses to a MEMBER OF THE PUBLIC from Iodine-131 Iodine-133, tritium, and all radionuclides in

. particulate form with half lives greater than 8 days in gaseous effluents released from each unit to areas beyond the SITE BOUNDARY conforming

.to Appendix I to 10 CFR 50,

10) Limitations on the annual dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and to radiation from uranium fuel cycle sources conforming to 40 CFR Part 190.

f. Radiological Environmental Monitoring Program

[

A program shall be provided to monitor the radiation and radio nuclides in the environs of the plant. The program shall provide (1) representative measurements of radioactivity in the highest potential exposure pathways, and (2) verification of the accuracy of the effluent monitoring program and modeling of environmental exposure pathways. The program shall (1) be contained in the ODCM, (2) conform to the guidance of Appendix I to 10 CFR Part 50, and (3) include the following:

-1)

Monitoring, sampling, analysis, and reporting of radiation and radionuclides in the environment in accordance with the methodology and parameters in the

ODCM, 2)

A Land Use Census to ensure that changes in the use of areas at and beyond

the SITE BOUNDARY are identified and that modifications to the monitoring program are made if required by the results of this census, and 3)

Participation in a Interlaboratory Comparison Program to ensure that independent checks on the precision and accuracy of the measurements of radioactive materials in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring.

g. Cnnfiguratinn Rid Management Program

' The Configuration Risk Management Program (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 program shall include the following elements:

- 1) Provisions for the control and implementation of a Level 1, at power, internal events, PRA-informed methodology. The assessment shall be capable of evaluating the applicable plant configuration.

2) Provisions for performing an assessment prior to entering the LCO Action Statement for planned activities.

NORTH ' ANNA - UNIT 1 6-13c Amendment No. 430,214

ADMINISTRATIVE CONTROLS 3 Cnnfiguratinn Rick Management Program (continued)

3) Provisions for performing an assessment after entering the LCO Action Statement for unplanned entry into the LCO Action Statement.

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

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

Current risk-informed action statements include: Action 3.8.1.1.b 63 REPORTING REOUIREMFNTS ROUTINE REPORTS 6.9.1 In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following reports shall be submitted to the Director of'he Regional Office of Inspection and Enforcement unless otherwise noted.

STARTUP REPORTS 6.9.1.1 A summary report of plant startup and power escalation testing shall be submitted following (a) receipt of an opersing license, (2) amendment to the license involving a planned increase in power level, (3) installation of fuel that has a different design or has been manufactured by a different fuel supplier, and (4) modifications that may have significantly altered the nuclear, thermal, or hydraulic performance of the plant.

6.9.1.2 The startup report shall address each of the tests identified in the FSAR and shall include a description of the measured values of the operating conditions or characteristics obtained during the test program and a comparison of these values with design predictions and specifications. Any corrective actions that were required to obtain satisfactory operation shall also be described. Any additional specific details requested in license conditions based on other commitments shall be included in this report.

6.9.1.3 Startup reports shall be submitted within (1) 90 days following completion of the startup test program, (2) 90 days following resumption or commencement of commercial power operation, or (3) 9 months following initial criticality, whichever is earliest. If the Startup Report does not cover all three events (i.e., initial criticality, completion of startup test program, and resumption or commencement of commercial power operation), supplementary reports shall be submitted at least every three months until all three events have been completed.

r NORTH ANNA - UNIT 1 6-14 Amendment No. 4,214

p%*:09 g

UNITED STATES g

j NUCLEAR REGULATORY COMMISSION 4

WASHINGTON, D.C. 30006 4001

'+9.....,o 1

i 4

VIRGINIA ELECTRIC AND POWER COMPANY OLD DOMINION ELECTRIC COOPERATIVE DOCKET NO. 50-339 NORTH ANNA POWER STATION. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.195 License No. NPF-7 1.

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

A.

The application for amendment by Virginia Electric and Power Company et al., (the licensee) dated September 1,1995, as supplemented April 8,1996; April 22,1996; April 23,1996; November 18,1997; February 9,1998; March 25,1998; May 5,1998; June 25,1998, and June 29,1998, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; 1

C.

There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

,. 2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility

{

Operating License No. NPF-7 is hereby amended to read as follows:

L

-(2)

Technical Specifications i

1 l

The Technical Specifications contained in Appendices A and B, as revised through l

Amendment No. 195, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

i 3.

In addition, the license is amended to add paragraph 2.1. to the Facility Operating License No. NPF-7 as follows:

,l-L 2.1.

Additional Conditions l

The Additional Conditions contained in Appendix C, as revised through Amendment l

No. 195

, are hereby incorporated into this license. Virginia Electric and Power

. Company shall operate the facility in accordance with the Additional Conditions.

4.

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

FOR THE NUCLEAR REGULATORY COMMISSION h

P. T. Kuo, Acting D rector

'U j

Project Directorate ll-1 Division of Reactor Prcjects - 1/11 Office of Nuclear Reactor Regulation

(.

Attachments:

1. Page 13 of License No. NPF-7

2. Appendix C to License No. NPF-7

3. Changes to the Technical Specifications Date of lasuance: August,26,,1998 l

m l

i ATTACHMENT TO LICENSE AMENDMENT NO.195 l

TO FACILITY OPERATING LICENSE NO. NPF-7 DOCKET NO. 50-339 Replace the following pages of the Operating License with the enclosed pages. The revised pages are identified by Amendment number and contain vertical lines indicating the areas of i

change.

Remove Paaes Insert Paoes 13 13 Appendix C Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages as indicated. The revised pages are identified by amendment number and contain verticallines indicating the areas of change. Overleaf page B 3/4 0-1 is included for document completeness.

Remove Paaes Insert Paoes 1-3 1-3 3/4 8-1 3/4 8-1 3/4 8-2 3/4 8-2 3/4 8-2a 3/4 8-2a 3/4 8-3 3/4 8-3 3/484 3/484 3/4 8-5 3/4 8-5 3/4 8-6 3/4 8-6 3/4 84a 3/4846 3/4 8 3/4 8-9 3/4 8-10 3/4 8-10 B 3/4 0-2 B 3/4 0-2 B 3/41-3 B 3/4 1-3 8 3/4 8-1 B 3/4 8-1 B 3/4 8-2 B 3/4 8-2 B 3/4 8-3 6-14c 6-14c 6-14d 6-14d i

)

-l l

' 1 2.E. The licensee shall fully implement and maintain in effect all provisions of the Commission-

{

approved physical security, guard training and qualification, and safeguards contingency j

plans including amendments made pursuant to provisions of the Miscellaneous j

t Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The plans, which contain Safeguards Information protected under 10 CFR 73.21, are entitled: " North Anna l

Power Station Physical Security Plan," with revisions submitted through February 24, 1988; " North Anna Power Station Guard Training and Qualification Plan," with revisions

. submitted through May 14,1987; and " North Anna Power Station Safeguards Contingency Plan," with revisions submitted through January 9,1987. Changes made in accordance with 10 CFR 73.55 shall be implemented in accordance with the schedule set forth therein.

l 2.F. The design of the reactor coolant pump and steam generator supports may be revised in accordance with the licensee's submittal dated November 6,1986 (Serial No. 86-477A).

2.G. If VEPCO plans to remove or to make significant changes in the normal operation of l

equipment that controls the amount of radioactivity in effluents from the Narth Anna Power l

Station, the NRC shall be notified in writing regardless of whether the change affects the amount of radioactivity in the effluents.

I-l 2.H. VEPCO shall report any violations of the requirements contained in Section 2, items C.(3)

J through C.(21), E, F and G of this license within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by telephone and confirmed by telegram, mailgram, or facsimile transmission to the Director of the Regional Office, or his

. designate, no later than the first working day following the violation, with a written followup report within 14 days.

2.1.

Additional Conditions l

The Additional Conditions contained in Appendix C, as revised through Amendment No.

l 195, are hereby incorporated into this license. Virginia Electric and Power Company shall operate the facility in accordance with the Additional Conditions.

Amendment No. W,W,4%,4M,195 t

1

b' APPENDlX C ADDITIONAL CONDITION FACILITY OPERATING LICENSE NO. NPF-7 Amendment Iraplementation Number Additional Condition:

Date 195 The licensee shall implement a procedure that will Prior to prohibit entry into an extended Emergency Diesel implementation of Generator Outage Time (14 days), for scheduled Amendment maintenance purposes, if severe weather conditions No. 195 are expected, as described in the licensee's application dated June 25,1998, and evaluated in the staffs Safety Evaluation dated August 26, 1998.

l i

I A

3]43 ELECTRICAL POWER SYSTEMS 3/4,8,1 A.C. SOURCES OPERATING LIMITING CONDITION FOR OPERATION 3.8.1.1

- As a minimum, the following A.C. electrical power sources shall be OPERABLE:

a.

Two physically independent circuits between the offsite transmission network and the onsite Class 1E distribution system, and b.

Two separate and independent emergency diesel generators (EDGs):

l

1. Each with a separate day tank containing a minimum of 450 gallons of fuel, and

2. A fuel storage system consisting of two underground storage tanks each containing a minimum of 45,000 gallons of fuel (This is a shared system with Unit 1), and

3. A separate fuel transfer system.

APPLICABILITY:

MODES 1,2,3 and 4.

ACTION:

With one offsite circuit of 3.8.1.1.a inoperable, demonstrate the OPERABILITY of a.

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 <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> thereafter. Restore the offsite circuit to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

b.

(Risk Informed) With one EDG of 3.8.1.1.b inoperable, demonstrate the OPERABILITY of the offsite A.C. power sources by performing Surveillance i

Requirement 4.8.1.1.1.a within I hour and at leap. once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> thereafter. If the EDG is inoperable due to any cause other than an inoperable support system, an l

independently testable component, or preplanned preventive maintenance or testing, demonstrate the OPERABILITY of the remaining OPERABLE EDG by performing Surveillance Requirement 4.8.1.1.2.a.4 within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> *, unless the absence of any potential common mode failure for the remaining EDG is demonstrated. Restore the EDG to OPERABLE status within 14 days if the AAC DG and the opposite unit's EDGs are OPERABLE or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />. In addition:

I This action is required to be completed regardless of when the inoperable EDG is restored to OPERABILITY NORTH ANNA - UNIT 2 3/4 8-1 Amendment No. 48, i 12.165,

+B4,195 1

-_____-_-_=___-____-___-_a

5 1.0 DEFINITIONS (Continued) i ENGINFFRFD SAFFTY FEATURE RFSPONSF TIME 1.12 The ENGINEERED S AFETY FEATURE RESPONSE TIME shall be that time interval from when the monitored parameter exceeds its ESF actuation setpoint at the channel sensor until the ESF equipment is capable of performing its safety function (i.e., the valves travel to their required positions, pump discharge pressures reach their required values, etc.). Times shall include emergency diesel generator staning and sequence loading delays where applicable.

l FREOUENCY NOTATION 1.13 The FREQUENCY NOTATION specified for the performance of Surveillance Requirements shall correspond to the intervals defined in Table 1.2.

- FUI I.Y WITHDR AWN 1.13a The control bank FULLY WITHDRAWN position shall be within the interval of 225 to 229 steps withdrawn, inclusive. Definition of the FULLY WITHDRAWN position for each specific cycle shall be documented in the rod insertion limit operator curve.

GASFOUS R ADWASTE TREATMENT SYSTEM 1.14 A G ASEOUS RADWASTE TREATMENT SYSTEM is the system designed and installed to reduce radioactive gaseous effluents by collecting primary coolant system offgases from the primary system and providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment. The system is composed of the waste gas decay tanks, regenerative heat exchanger, waste gas charcoal filters, process vent blowers, waste gas surge tanks and waste gas diaphragm compressor.

IDENTIFTFD 1 F AK AGE l

j 1.15 IDENTIFIED LEAKAGE shall be:

Leakage (except CONTROLLED LEAKAGE) into closed systems, such as pump a.

!~

seal or valve packing leaks that are captured and conducted to a sump or collecting i

tank, or b.

Leakage into the containment atmosphere from sources that are both specifically j

located and known either not to interfere with the operation of leakage detection systems or not to be PRESSURE BOUNDARY LEAKAGE, or c.

Reactor coolant system leakage through a steam generator to the secondary system.

j-MFMBER(S) OF THF PUBI TC 1.16 MEMBER (S) OF THE PUBLIC shall include all individuals who by virtue of their

- occupational status have no formal association with the plant. This category shall include non-employees of the licensee who are permitted to use portions of the site for recreational, occupational, or other purposes not associated with plant functions. This category shall not include non-employees such as vending machine servicemen or postman who, as part of their formaljob function, occasionally enter an area that is controlled by the licensee for purposes of protection of individuals from exposure to radiation and radioactive materials.

I

- NORTH ANNA - UNIT 2 1-3 Amendment No. 3!,130, ! 33,195 j

l l

1

---

~-- - --------- - - -

1 3L4,8 FI FCTRICAL POWER SYSTEMS 3/4.8.1 A.C. F SURPFS OPERATING LIMITING CONDITION FOR OPERATION 3.8.1.1 As a minimum, the following A.C. electrical power sources shall be OPERABLE:

i Two physically independent circuits between the offsite transmission network and a.

I the onsite Class IE distribution system, and b.

Two separate and independent emergency diesel generators (EDGs):

l l

l. Each with a separate day tank containing a minimum of 450 gallons of fuel, and l

2. A fuel storage system consisting of two underground storage tanks each i

containing a minimum of 45,000 gallons of fuel (This is a shared system with Unit 1), and l

3. A separate fuel transfer system.

APPLICABIT ITY-MODES 1,2,3 and 4.

ACTION-With one offsite circuit of 3.8.1.1.a inoperable, demonstrate the OPERABILITY of a.

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 <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> thereafter. Restore the offsite circuit to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

b.

(Risk-Informed) With one EDG of 3.8.1.1.b inoperable, demonstrate the l

OPERABILITY of the offsite A.C. power sources by performing Surveillance Requirement 4.8.1.1.1.a within I hour and at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> thereafter. If the EDG is inoperable due to any cause other than an inoperable support system, an l

independently testable component, or preplanned preventive maintenance or testing, demonstrate the OPERABILITY of the remaining OPERABLE EDG by performing Surveillance Requirement 4.8.1.1.2.a.4 within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> *, unless the absence of any potential common mode failure for the remaining EDG is demonstrated. Restore the EDG to OPERABLE ~ status within 14 days if the AAC DG and the opposite uni 's EDGs are OPERABLE or be in at least HOT t

STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />. In addition:

l-l This action is required to be completed regardless of when the inoperable EDG is restored to OPERABILITY NORTH ANNA - UNIT 2 3/48-1 Amendment No. 48, ! !2,155,104,195

l i

Fi FCTRICAI POWER SYSTEMS LIMITING CONDITION FOR OPERATION ACTION * (Continued)

1. If one or more of the three diesel generators (i.e., AAC DG or opposite unit's EDGs) required for entry into the 14 day action statement is(are) inoperable at the start of the 14 day action statement, restore the diesel generator (s) to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the next following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

\\

2. If one or more of the three diesel generators (i.e., AAC DG or opposite unit's EDGs) required for entry into the 14 day action statement become(s) inoperable f

during the 14 day action statement, restore the diesel generator (s) to J

OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the next following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

With one offsite circuit and one EDG inoperable, demonstrate the OPERABILITY c.

of the remaining A.C. sources by performing Surveillance Requirement 4.8.1.1.1.a within one hour and at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> thereafter; and if the EDG became inoperable due to any cause other than an inoperable support system, an independently testable component, or preplanned preventative maintenance or testing, demonstrate the OPERABILITY of the remaining OPERABLE EDG by performing Surveillance Requirement 4.8.1.1.2.a.4 within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> *, unless the absence of any potential common mode failure for the remaining EDG is l

demonstrated. Restore one of the inoperable sources to OPERABLE status within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />. Restore the other A.C. power source (offsite circuit or EDG) to OPERABLE status in accordance with the provisions of l

Section 3.8.1.1 Action Statement a or b, as appropriate with the time requirement of that Action Statement based on the time ofinitial loss of the remaining inoperable A.C. power source.

l d.

With two of the required offsite A.C. circuits inoperable, restore one of the inoperable offsite sources to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. Following restoration of one offsite source, follow Action Statement a with the time requirement of that Action Statement based on the time ofinitialloss of the remaining inoperable offsite A.C.

circuit.

l f

(

This action is required to be completed regardless of when the inoperable EDG is restored to OPERABILITY.

NORTH ANNA - UNIT 2 3/4 8-2 Amendment No. AS,70, !65,195 i

l A

6 Fi FCTRICAL POWFR SYSTFMS LIMITING CONDITION FOR OPERATION ACTION- (Continued 9 With two of the above required EDGs inoperable, demonstrate the OPERABILITY e.

of two offsite A.C. circuits by performing Surveillance Requirement 4.8.1.1.1.a within one hour and at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> thereafter; restore one of the inoperable EDGs to OPERABLE status within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />. Following restoration of one EDG, follow Action Statement b with the time requirement of that Action Statement based on the time ofinitialloss of the remaining inoperable EDO.

f.

With one underground fuel oil storage tank of 3.8.1.1.b.2 inoperable for the performance of Surveillance Requirement 4.8.1.1.4 or for tank repairs:

1. Verify 45,000 gallons of fuel is available in the operable underground fuel oil storage Yk at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />,

2. Verify a ininimum of 100,000 gallons of fuel is maintained in the above ground l

main fuel oil storage tank at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />,

3. Verify an available source of fuel oil and transportation to supply 50,000 gallons of fuel in less than a 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> period, and

4. Restore the storage tank to OPERABLE status within 7 days or place both Units in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

I l

NORTH ANNA - UNIT 2 3/4 8-2a Amendment No. 444,195 L

F1 FCTRICAI. POWER SYSTEMS SURVEILLANCE REQUIREMENTS 4.8.1.1.1 Each of the above required physically independent circuits between the offsite transmission network and the onsite Class IE distribution system shall be:

1 Determined OPERABLE at least once per 7 days by verifying correct breaker a.

l alignment indicating power availability.

b.

Demonstrated OPERABLE at least once per 18 months during shutdown by manually transferring the onsite Class IE power supply from the normal circuit to the alternate circuit.

4.8.1.1.2 Each emergency diesel generetor (EDG) shall be demonstrated OPERABLE:

l In accordance with the frequency specified in Table 4.6. on a STAGGERED l

a.

TEST BASIS by:

1. Verifying the fuel level in the day tank.

2. Verifying the fuel level in the fuel storage tank.

3. Verifying the fuel transfer pump can be started and transfers fuel from the storage system to the day tank.

4. Verifying the EDG can start ** and gradually accelerate to synchronous speed l

(900 rpm) with generator voltage and frequency at 4160 i 420 volts and 60 i 1.2 Hz. Subsequently, verifying the generator is synchronized, gradually loaded ** to an indicated 2500-2600 kw* *

• and operates for at least 60 minutes.

5. Verifying the EDG is aligned to provide standby power to the associated emergency busses.

b.

At least once per 92 days by verifying that a sample of diesel fuel from the fuel storage tank obtained as a DR AIN sample 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.

c.

At least once per 184 days, the EDG shall be started ** and accelerated to at least l

900 rpm in less than or equal to 10 seconds. The generator voltage and frequency shall be 4160 i 420 volts and 60 i 1.2 Hz within 10 seconds after the start signal.

This test sLdl be conducted in accordance with the manufacturer's recommendations regarding engine prelube and warmup procedures, and as applicable regarding loading recommendations.

l This band is meant as guidance to avoid routine overloading of the engine. Loads in excess of this band for special testing under direct monitoring of the manufacturer or momentary variations due to changing bus loads shall not invalida'e the test.

l NORTH ANNA - UNIT 2 3/48-3 Amendment No. 44,195 L

F o

V O

Fi FCTRICAL POWER SYSTEMS l

SURVEILLANCE REQUIREMENTS l

4.8.1.1.2 (Continued) l The EDG shall be manually synchronized to its appropriate emergency bus, l

gradually loaded" to an indicated 2500 to 2600 kw'**, and operated for at least 60 minutes. The EDG shall be started for this test by using one of the following l

signals on a rotating test basis:

a)

Simulated loss of offsite power by itself.

b)

Simulated loss of offsite power in conjunction with an ESF actuation test signal.

c)

An ESF actuation test signal by itself.

This test, ifit is performed so it coincides with the testing required by Surveillance Requirement 4.8.1.1.2.a.4, may also serve to concurrently meet those requirements as well.

d.

At least once per 18 months during shutdown by:

1.

Verifying that, on rejection of a load of greater than or equal to 610 kw, the l

vol age and frequency are maintained with 4160i 420 volts and 60 1.2 t

Hz.

2.

Verifying that the load sequencing timers are OPERABLE with times l

within the tolerances shown in Table 4.8-1.

3.

Simulating a loss of offsite power by itself, and:

l a) Verifying de-energization of the emergency busses and load shedding from the emergency busses.

b) Verifying the EDO starts ** on the auto-start signal, energizes the j

emergency busses with permanently connected loads within 10 seconds, energizes the auto-connected shutdown loads through the sequencing timers and operates for greater than or equal to 5 minutes while its generator is loaded with the shutdown loads. After energization of these loads, the steady state voltage and frequency shall be maintained at 4160i420 volts and 60 1.2 Hz.

This test shall be conducted in accordance with the manufacturer's recommendations regarding engine prelube and warmup procedures, and as applicable regarding loading recommendations.

This band is meant as guidance to avoid routine overloading of the engine. Loads in excess of this band for special testing under direct monitoring of the manufacturer or momentary variations due to changing bus loads shall not invalidate the test.

i NORTH ANNA - UNIT 2 3/48-4 Amendment No. 70. !65,195

I

, +

FI FPTRICAI POWER SYSTFMS SURVEILLANCE REQUIREMENTS F

4.8.1.1.2 (Continued)-

4.

Verifying that on an ESF actuation test signal (without loss of offsite power) the EDG starts *

• on the auto-start signal and operates on standby for greater than or equal to 5 minutes.

5.

Simulating a loss of offsite power in conjunction with an ESF actuation test l-signal, and a) Verifying de-energization of the emergency biisses and load shedding from the emergency busses.

b) Verifying the EDG starts" on the au:o-start signal, energizes the l

emergency busses with permanently connected loads within 10 seconds, energizes the auto-connected emergency (accident) loads through the sequencing timers and operates for greater than or equal to 5 minutes and maintains the steady state voltage and frequency at 4160i420 volts and 60 1.2 Hz.

c) Verifying that all EDG trips, except engine overspeed, generator l

differential and breaker overcurrent are automatically bypassed upon loss of voltage on the emergency bus and/or a safety injection actuation signal.

6.

Verifying the EDG operates *

• for at least 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. During the first 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> of this test, the EDG shall be loaded to an indicated target value of 2950 kw (between 2900-3000 kw)"* and during the remaining 22 hours2.546296e-4 days <br />0.00611 hours <br />3.637566e-5 weeks <br />8.371e-6 months <br /> of this test, the EDG shall be loaded to an indicated 2500-2600 kw"*.

. 7.

. Verifying that the auto-connected loads to each EDG do not exceed the 2000 hour0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br /> rating of 3000 kw.

8.

Verifying the EDG's capability to:

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

This test shall be conducted in accordance with the manufacturer's recommendations regarding engine prelube and warmup procedures, and as applicable regarding loading recommendations.

g

• *

• This band is meant as guidance to avoid routine overloading of the engine. Loads in excess of this band for special testing under direct monitoring of the manufacturer or momentary variations due to changing bus loads shall not invalidate the test.

NORTH ANNA - UNIT 2.

3/48 Amendment No. 42, iS, !65,195

_- - - _ __ ___ O

e 4.

FI FCTRICAI. POWER SYSTEMS SURVEILLANCE REQUIREMEN"G 4.8.1.1.2 (Continued) 9.

Verifying that the following EDG lockout features prevent EDG starting

[

only when required:

a) Remote Local Selection Switch b) Emergency Stop Switch 10.

Verifying the EDG's hot restart capability by:

) Operating the EDG** loaded to an indicated 2500 to 2600 kw'** for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or until operating temperatures have stabilized, and b) Within 5 minutes of shutdown verify the EDG can be started ** and l

accelerated to at least 900 rpm in less than or equal to 10 seconds. The generator voltage and frequency shall be 4160 420 volts and 60

• 1.2 Hz within 10 seconds after the start signal.

At least once per 10 years or after any modifications which could affect EDG e.

interdependence by staning** both EDGs simultaneously, during shutdown, and verifying that both EDGs accelerate to at least 900 rpm in less than or equal to 10 seconds.

f.

At least once per 24 months during any mode of operation, by subjecting each EDG to a preventive maintenance inspection in accordance with maintenance procedures appropriate for diesels used for this class of standby service.

4.8.1.1.3 Each emergency diesel generator 125-volt battery bank and charger shall be demonstrated OPERABLE:

a.

At least once per 7 days by verifying that:

1.

The parameters in Table 4.8-3 meet Category A limits and 2.

The total battery terminal voltage is 2129 volts on a float charge.

f 1

This test shall be conducted in accordance with the manufacturer's recommendations 1

regarding engine prelube and warmup procedures, and as applicable regarding loading recommendations.

r l'

This band is meant as guidance to avoid routine overloading of the engine. Loads in excess of this band for special testing under direct monitoring of the manufacturer or momentary variations due to changing bus loads shall not invalidate the test.

NORTH ANNA - UNIT 2 3/4 8-6 Amendment No, is,81, !65,195 l

1 i

}

l FI FCTRICAL POWER SYSTEMS SURVEILLANCE REQUIREMENTS 4.8.1.1.3 (continued) l I

b.

At least once per 92 days and within 7 days after a battery discharge where the battery terminal voltage decreased below 110 volts or battery overcharge above 150 volts, by verifying that:

1.

The parameters in Table 4.8-3 meet Category B limits and 2.

There is no visible corrosion at either terminals or connectors, or the connection resistance of these items is less than 150 x 10 to the minus 6 ohms.

At least once per 18 months by verifying that:

c.

1.

The cells, cell plates and battery racks show no visual indication of physical 4

damage or abnormal deterioration.

2.

The cell-to-cell and terminal connections are clean, tight and coated with anti corrosion material.

3.

The resistance of each cell-to-cell and terminal connection is less than or equal to 150 x 10-6 ohms.

4.

The battery charger will supply at least ten amperes at 125 volts for at least 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

d.

At least once per 60 months, during shutdown, by verifying that the battery capacity is at least 80% of the manufacturer's rating when subjected to a performance discharge test.

At least once per 18 months, during shutdown, perform a performance discharge e.

test of battery capacity if the battery shows signs of degradation or has reached 85%

of its service life expected for the application. Degradation is indicated when the battery capacity drops more than 10% of rated capacity from its average from previous performance discharge tests, or is below 90% of the manufacturer's rating.

4.8.1.1.4 For each underground EDG fuel oil storage tank perform the following at least once l

per 10 years:

1.

Drain each fuel oil storage tank 2.

Remove sediment from each fuel oil storage tank 3.

Inspect each fuel oil storage tank for integrity 4.

Clean each fuel oil storage tank NORTH ANNA - UNIT 2 3/4 8-6a Amendment No. '7, ', S1, ! !2,195

_ _ ~

Table 4 R-7 EMERGFNCY DIFRFI. GFNERATOR TEST SCHFnUI F l

Number of Failures in Number of Failures in I.nct 20 Valid Testc*

Iact 100 Valid Testc*

Test Frequcacy 51 54 Once per 31 days 2 2**

25 Once per 7 days 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, but determined on a per emergency diesel generator basis.-

For the purposes of determining required test frequency, the previous test failure count may be reduced to zero if a complete diesel overhaul to like-new conditions is completed, provided that the overhaul including appropriate post-maintenance operation and testing,is specifically approved by the manufacturer and if acceptable reliability has been demonstrated. The reliability criterion shall be the successful completion of 14 consecutive tests in a single series. Ten of these tests shall be in accordance with Surveillance Requirement 4.8.1.1.2.a.4; four tests,in accordance with Surveillance Requirement 4.8.1.1.2.c. If this criterion is not satisfied during the first series of tests, any altemate criterion to be used to transvalue the failure count to zero requires NRC approval.

The associated test frequency shall be maintained until seven consecutive failure free demands have been performed and the number of failures in the last 20 valid demands has been reduced to one.

i

. NORTH ANNA - UNIT 2 3/4 8-9 Amendment No. 48,195 l

FI FCTRICAL POWER SYSTEMS SHliTDOWN LIMITING CONDITION FOR OPERATION 3.8.1.2 As a minimum, one of the following trains of A.C. electrical power sources shall be OPERABLE:

One circuit between the offsite transmission network and the onsite Class IE a.

distribution system, and b.

One emergency diesel generator with:

l

1. A day tank containing a minimum volume of 450 gallons of fuel;

2. A fuel storage system consisting of two underground storage tanks each containing a minimum volume of 45,000 gallons of fuel (This is a shared system with Unit 1), and

3. A fuel transfer system.

APPI TCABII TTY:

a.

Modes 5 and 6 b.

During movement ofirradiated fuel assemblies or loads overirradiated fuel assemblies when no fuel assemblies are in the reactor vessel.

ACTION-With less than the above minimum required A.C. electrical power sources a.

OPERABLE, immediately suspend all operations involving CORE ALTERATIONS, positive reactivity changes, movement of in adiated fuel assemblies, and movement of loads over irradiated fuel assemblies until the minimum required A.C. electrical power sources are restored to OPERABLE status.

b.

With one underground fuel oil storage tank of 3.8.1.2.b.2 inoperable for the performance of Surveillance Requirement 4.8.1.1.4 or for tank repairs:

1. Verify 45,000 gallons of fuel is available in the operable underground fuel oil storage tank at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />,

2. Verify a minimum of 100,000 gallons of fuel oil is maintained in the above ground main fuel oil storage tank at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />,

3. Verify an available source of fuel oil and transportation to supply 50,000 gallons of fuel in less than a 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> period, and

4. Restore the storage tank to OPERABLE status within 7 days or place both Units in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />, and perform ACTION a. above.

SURVEILLANCE REQUIREMENTS 4.8.1.2 The above required A.C. electrical power sources shall be demonstrated OPERABLE by the performance of each of the Surveillance Requirements of 4.8.1.1.1,4.8.1.1.2,4.8.1.1.3, and 4.8.1.1.4.

NORTH ANNA - UNIT 2 3/4 8-10 Amendment No. AP,70, !!2, !38, 434,195 l

I 3/4.0 APPLICABILITY BASES The specifications of this section provide the general requirements appli-cable to each.of the Limiting Conditions for Operation and Surveillance Require-j ments within Section 3/4.

i 3.0.1 This specification defines the applicability of each specification in j

terms of defined OPERATIONAL MODES or other specified conditions and is provided l

to delineate specifically when each specification is applicable.

3.0.2 This specification defines those conditions necessary to constitute compliance with the terms of an individual Limiting Condition for Operation and associated ACTION requirement.

3.0.3 This specification delineates the ACTION to be taken for circumstances not directly provided for in the ACTION statements and whose occurrence would violate the intent of the specification.

For example, Specification 3.5.1 requires each Reactor Coolant System accumulator to be OPERABLE and provides explicit ACTION requirements if one accumulator is inoperable. Under the terms of Specification 3.0.3, if more than one accumulator is inoperable, the unit is required to be in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in at least HOT l

SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. As a further example, Specification 3.6.2.1 requires two Quench Spray Systems to be OPERABLE and provides explicit ACTION requirements if one spray system is inoperable.

Under the terms of Specification 3.0.3, if both of the required Quench Spray Systems are inoperable, within one hour measures must be initiated to place the unit in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, in at least HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and in at least COLD SHUTDOWN in the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

3.0.4 This specification provides that entry into an OPERATIONAL MODE or other specified applicability condition must be made with (a) the full comple-ment of required systems, equipment or components OPERABLE and (b) all other parameters as specified in the Limiting Conditions for Operation being met without regard for allowable deviations and out-of-service provisions contained in the ACTION statements.

The intent of this provision is to insure that facility operation is not initiated with either required equipment or systems inoperable or other speci-fied limits being exceeded.

NORTH ANNA - UNIT 2 B 3/4 0-1 Amendment No.

46 1

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P APPI ICARII TTY BASES 3.0.5 This specification delineates what additional conditions must be satisfied to permit L

operation to continue, consistent with the ACTION statements for power sources, when a normal or emergency power source is not OPERABLE. It specifically prohibits operation when one division is inoperable because its normal or emergency power source is inoperable and a system, subsystem, train, component or device in another division is inoperable for another reason.

The provisions of this specification permit the ACTION statements associated with individual systems, subsystems, trains, components, or devices to be consistent with the ACTION

- statements of the associated electrical power source. It allows operation to be governed by the time limits of the ACTION statement associated with the Limiting Condition for Operation for the normal or emergency power source, not the individual ACTION statements for each system, subsystem, train, component or device that is determined to be inoperable solely because of the inoperability ofits normal or emergency power source.

For example, Specification 3.8.1.1 requires in part that two emergency diesel generators be OPERABLE. The ACTION statement provides for an out-of-service time when one emergency l

diesel generator is not OPERABLE. If the definition of OPERABLE were applied without consideration of Specification 3.0.5, all systems, subsystems, trains, components and devices supplied by the inoperable emergency power source would also be inoperable. This would dictate invoking the applicable ACTION statements for each of the applicable Limiting Conditions for Operation. However, the provisions of Specification 3.0.5 permit the time limits for continued l

operation to be consistent with the ACTION statement for the inoperable emergency diesel generator instead, provided the other specified conditions are satisfied. In this case, this would.

mean that the corresponding normal power source must be OPERABLE, and all redundant systems, subsystems, trains, components, and devices must be OPERABLE, or otherwise satisfy Specification 3.0.5 (i.e., be capable of performing their design fimetion and have at least one normal or one emergency power source OPERABLE). If they are not satisfied, shutdown is required in accordance with this specification.

As a further example, Specification 3.8.1.1 requires in part that two physically independent L

circuits between the offsite transmission network and the onsite Class IE distribution system be OPERABLE The ACTION statement provides a 24-hour out-of-service time when both required

. offsite circuits are not OPERABLE. If the definition of OPERABLE were applied without consideration of Specification 3.0.5, all systems, subsystems, trains, components and devices supplied by the inoperable normal power source, both of the offsite circuits, would also be inoperable. This would dictate invoking the applicable ACTION statements for each of the applicable LCOs. However, the provisions of Specification 3.0.5 permit the time limits for continued operation to be NORTH ANNA - UNIT 2 B 3/4 0-2 Amendment No.195 b_______-_____

r RFACTIVITY CONTROI SYSTEMR BASES 3/4.1.2 BOR ATION SYSTEMS

)

The boron injection system ensures that negative reactivity control is available during each

. mode of facility operation. The components required to perform this function include 1) borated water sources,2) charging pumps,3) separate flow paths,4) boric acid transfer pumps,5) associated heat tracing systems, and 6) an emergency power supply from OPERABLE emergency l

diesel generators.

With the RCS average temperature above 200*F, a minimum of two boron injection flow f

paths are required to ensure single functional capability in the event an assumed failure renders one l

of the flow paths inoperable. The boration capability of either flow path is sufficient to provide a i

SHUTDOWN M ARGIN from expected operation conditions of 1.77% delta k/k after xenon decay and cooldown to 200*F. The maximum expected boration capability requirement occurs at EOL from full power equilibrium xenon conditions and requires 6000 gallons of 12,950 ppm borated

)

water from the boric acid storage tanks or 54,200 gallons of 2300 ppm borated water from the

{

refueling water storage tank.

With the RCS temperature below 200 F, one injection system is acceptable without single failure consideration on the basis of the stable reactivity condition of the reactor and the additional restrictions prohibiting CORE ALTERATIONS and positive reactivity change in the event the single injection system becomes inoperable.

The limitation for a maximum of one charging pump to be OPERABLE and the Surveillance Requirement to verify all charging pumps except the required OPERABLE pump to be inoperable below 270 F provides assurance that a mass addition pressure transient can be relieved by the operation of a single PORV.

Having more than one charging pump OPERABLE during pump switching operations is i

allowed. This is acceptable based on pump switching being a momentary action under the direct

]

administrative control of a licensed operator. Rendering a charging pump inoperable for this requirement may be accomplished by methods such as placing the control switch in the pull-to-l lock position, tagging of the power supply breaker, or closing of the pump discharge valve. If the pump discharge valve is used to render a pump inoperable during solid water operation, the valve will be deenergized and tagged in the closed position.

The boron capability required below 200*F is sufficient to provide a SHUTDOWN MARGIN of 1.77% delta k/k after zenon decay and cooldown from 200 F to 140 F. This condition requires either 1378 gallons of 12,950 ppm borated water from the boric acid storage tanks or 3400 gallons of 2300 ppm borated water from the refueling water storage tank.

I NORTH ANNA - UNIT 2 B 3/4 1-3 Amendment No. Si,78,119,

!?0,183, 195

o i

9 3LQ FI FCTRICAI POWER SYSTEMS BASES 3/4.R 1 and 3/4 Ri ALC. and D C. POWER SOURCFS AND DISTRIBUTION The OPERABILITY of the A.C. and D.C. power sources and associated distribution systems during operation ensures that sufficient power will be available to supply the safety related equipment required for 1) the safe shutdown of the facility and 2) the mitigation and control of accident conditions within the facility. The minimum specified independent and redundant A.C.

and D.C. power sources and distribution systems satisfy the requirements of General Design Criteria 17 of Appendix "A" to 10 CFR 50.

For each EDG, the fuel oil transfer system shall be capable of automatically transferring fuel oil to the associated EDG day tank in sufficient quantities to maintain adequate day tank level to support full load operation of the EDG.

The ACTION requirements specified for the levels of degradation of the power sources provide restriction upon continued facility operation commensurate with the level of degradation.

The OPERABILITY of the power sources are consistent with the initial condition assumptions of the accident analyses and are based upon maintaining at least one of each of the onsite A.C. and D.C. power sources and associated distribution systems OPERABLE during accident conditions coincident with an assumed loss of offsite power and single failure of the other onsite A.C. source.

Entering the 14 day EDG action statement during power operation has been shown to result in a smallincrease in the core damage frequency, provided the Alternate A.C. diesel generator (AAC DG)is OPERABLE and the opposite unit's EDGs are both OPERABLE. A Configuration Risk Management Program (CRMP) defined in Administrative Control Section 6.8.4.g is implemented to evaluate risk associated with the EDG outage. The EDG and AAC DG annual unavailability is limited by the Maintenance Rule Program.

When one or more of the diesel generators (i.e., AAC DG or opposite unit's EDGs) required to enter the 14 day actions statement is inoperable or becomes inoperable during the l

fourteen day action statement of the effected EDG, a 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> action statement is entered. If the

~ three diesel generators (i.e., AAC DG or opposite unit's EDGs) required to support entry into the i

I founeen day action statement are restored to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, the remainder of the 14 day action statement can be used. Restoring the affected EDG to service removes the l

conditional OPERABILITY requirements for the AAC DG and opposite unit's EDGs.

1 I

The operability requirements for the AAC DG are specified in the Technical Requirements Manual. In addition, to be considered OPERABLE to support the fourteen day action statement the l

AAC DG must be capable of providing power to the affected bus (i.e., connectable to the bus with j

the associated breakers and control power available.)If the AAC DG becomes inoperable

)

I NORTH ANNA - UNIT 2 B 3/4 8-1 Amendment No. 48,81, ! 38,184,195

'e

..c.

3/1g FIFrTRICAI POWER SYRTEMR BASES q

during the 14 day action statement, the OPERABILITY of the remaining EDGs does not need to be demonstrated since the AAC DG was designed and purchased acco Jing to specifications which d

adequately ensure that common cause failure in not likely.

The ACTION requirements specified in Modes 5 and 6 address the condition where sufficient power is unavailable to recover from postulated events (i.e., fuel handling accident).

Implementation of the ACTION requirements shall not preclude completion of actions to establish

. a safe conservative plant condition. Completion of the requirements will prevent the occurrence of

postulated events for which mitigating actions would be required.

The OPEP ABILRY of the minimum specified A.C. and D.C. power sources and associated distribu.on systems during shutdown and refueling ensures that 1) the facility can be j

maintained in the shutdown or refueling condition for extended time periods,2) sufficient

)

instrumentation and control capability is available for monitoring and maintaining the unit status, I

and 3) sufficient power is available for systems necessary to recover from postulated events in g

these MODES,'e.g., a fuel handling accident.

The Survemance Requnements for demonstrating the OPERABILITY of the Emergency l

Diesel Generators are in accordance with the recommendations of Regulatory Guide 1.9 " Selection of Diesel Generator Set Capacity for Standby Power Supplies," March 10,1971, and 1.108

" Periodic Testing of Diesel Generator Units Used as Onsite Electric Power Systems at Nuclear Power Plants" Revision 1,' August 1977, as modified by Amendment No. 48 issued August 22, 1986.

The Surveillance Requirements for demonstrating the OPERABILITY of the Emergency Diesel Generator batteries and the Station batteries are based on the recommendations of Regulatory Guide 1.129," Maintenance, Testing and Replacement of Large Lead Storage Batteries

' for Nuclear Power Plants," February 1978, and IEEE Std 450-1980, "IEEE Recommended Practice for Maintenance, Testing, and Replacement of Large Lead Storage Batteries for Generating

. Stations and Substations," as modified by Amendment No. 84 issued March 25,1988.

Containment electrical penetration and penetration conductors are protected by either de-energizing circuits not required during reactor operation or by demonstrating the OPERABILITY of primary and backup overcurrent protection circuit breakers during period surveillance.

l L

NORTH ANNA - UNIT 2 B 3/4 8-2 Amendment No. !?8, !Si,195

3L42 FI FrTRICAI_ POWER SYSTEMR BASES The surveillance frequency applicable to molded case circuit breakers and/or buses provides assurance of breaker and/or fuse reliability by testing at least one representative sample of each manufacturer's brand of circuit breaker and/or fuse. Each manufacturer's molded case circuit breakers and/or fuses are grouped into representative samples which are then tested on a rotating basis to ensure that all breakers and/or fuses are tested. If a wide variety exists within any manufacturer's brand of molded case circuit breakers and/or fuses, it is necessary to divide that manufacturer's breakers and/or fuses into groups and treat each group as a separate type of breaker or fuse for sur"eillance purposes.

The OPERABILITY of the motor-operated valves thermal and overload protection and/or

. bypass devices ensures that these devices will not prevent safety-related valves from performing their functicn. The Surveillance Requirements for demonstrating the OPERABILITY of these devices are in accordance with Regulatory Guide 1.106, " Thermal Overload Protection for Electric Motors on Motor-Operated Valves," Revision 1, March 1977.

NORTH ANNA - UNIT 2 B 3/4 8-3 Amendment No.195

P ADMINISTRATIVE CONTROLS 6.8.4.e Radioactive Effluent Controls Program (Cont.)

8) Limitations on the annual and quanerly air doses resulting from noble gases released in gaseous effluents from each unit to areas beyond the SITE BOUNDARY conforming to Appendix I to i0 CFR Pan 50,

9) Limitations on the annual and quanerly doses to a MEMBER OF THE PUBLIC from Iodine-131, Iodine-133, tritium, and all radionuclides in paniculate form with half-lives greater than 8 dayr % gaseous effluents released from each unit to areas beyond the SITE BOUNDARY conforming to Appendix I to 10 CFR 50,

10) Limitations on the annual dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and to radiation from uranium fuel cycle sources conforming to 40 CFR Part 190.

f, Rndinlogien1 Environmental Mnnitnring Program A program shall be provided to monitor the radiation and radio nuclides in the environs of the plant. The program shall provide (1) representative measurements of radioactivity in the highest potential exposure pathways, and (2) verification of the accuracy of the effluent monitoring program and modeling of environmental exposure pathways. The program shall (1) be contained in the ODCM, (2) conform to the guidance of Appendix I to 10 CFR Part 50, and (3) include the following:

1) Monitoring, sampling, analysis, and reponing of radiation and radionuclides in the environment in accordance with the methodology and parameters in the ODCM,

2) A Land Use Census to ensure that changes in the use of areas at and beyond the SITE BOUNDARY are identified and that modifications to the monitoring program are made if required by the results of this census, and

3) Panicipation in a Interlaboratory Comparison Program to ensure that independent checks on the precision and accuracy of the measurements of radioactive materials in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring.

g. Cnnfiguratinn Risk Manngement Program The Configuration Risk Management Program (CRMP) provides a proceduralized risk-informed assessment to manage the risk r.ssociated 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 program shall include the j

following elements:

1) Provisions for the control and implemer;tation of a 1.evel 1, at power, intemal events, PRA-informed methodology. The assessment shall be capable of evaluating the applicable plant configuration.

2) Provisions for performing an assessment prior to entering the LCO Action Statement for planned activities.

NORTH ANNA - UNIT 2 6-14c Amendment No. 444,195

s ADMINISTRATIVE CONTROLS Configuration Rick Management Progra'21(continued)

3) Provisions for performing an assessment after entering the LCO Action Statement for unplanned entry into the LCO Action Statement.

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

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

~

Current risk-informed action statements include: Action 3.8.1.1.b 63 RFPORTING REQUIREMENTS ROIITINF REPORTS 6.9.1 In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following repons shall be submitted to the Director of the Regional Office of Inspection and Enforcement unless otherwise noted.

STARTIJP REPORTS 6.9.1.1 A summary report of plant startup and power escalation testing shall be submitted following (a) receip' of an operating license, (2) anendment to the license involving a planned increase in powerlevel, (3) installation of fuel that has a different design or has been manufactured by a different fuel supplier, and (4) modifications that may have significantly altered the nuclear, thermal, or hydraulic performance of the plant.

NORTH ANNA - UNIT 2 6-14d l

Amendment No. 47'95! !i, l l

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