Text

Amends 64 & 49 to Licenses NPF-4 & NPF-7,respectively, Revising Tech Specs for Listed TMI Items
	ML20132F025
Person / Time
Site:	North Anna
Issue date:	06/28/1985
From:	Butcher E; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20132F032	List: ML20132F025;
References
	NUDOCS 8507180231
	Download: ML20132F025 (39)
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s.

i

p utb fg UNITED STATES

[

g NUCLEAR REGULATORY COMMISSION D

!j WASHINGTON, D. C. 20555 5

%g.... +,4 VIRGINIA ELECTRIC AND POWER COMPANY OLD DOMINION ELECTRIC COOPERATIVE DOCKET NO. 50-338 NORTH ANNA POWER STATION, UNIT N0. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 64 License No. NPF-4 1.

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

A.

The application for amendment by Virginia Electric and Power Company, et al., (the licensee) dated June 3 as supplemented June 9, 1983, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.

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

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

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

8507180231 050628 ADOCK 0500 0

gDR c.

. 2.

. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachnent 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 The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 64, are hereby incorporated in the licenue. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective within 7 days from the date of issuance.

FOR THE NUCLEAR REGULATORY CCFHISSION

~@.:. - 6.. e,I

,. Tl~.

(--

Edward J. Butcher, Acting Chief Operating Reactors Branch f3 Division of Licensing

Attachment:

Changes to the Technical Specifications Date of Issuance: June 28, 1985 o

4 e.

ATTACHMENT T0 1.ICENSE AMENDMENT NO. 64 TO FACILITY OPERATING LICENSE NO. NPF-4 DOCKET N0. 50-338 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 vertical lines indicating the area of change.

The corresponding overleaf pages are also provided to maintain document completeness.

Page V

XIII 3/4 3-36 3/4 3-36a 3/4 3-37 3/4 3-38 3/4 3-38a 3/4 3-49 3/4 3-50 3/4 3-51 3/4 4-36 3/4 6-33 8 3/4 4-13

C INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.4.2 SAFETY VALVES - SHUTD0WN................................

3/4 4-6 3/4.4.3 SAFETY VALVES - 0PERATING...............................

3/4 4-7 SAFETY and RELIEF VALVES - OPERATING Safety Va1ves...........................................

3/4 4-7 Relief Va1ves...........................................

3/4 4-7a 3/4.4.4 PRESSURIZER.............................................

3/4 4-8 3/4.4.5 STEAM GENERATORS........................................

3/4 4-9 3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE Leakage Detection Systems...............................

3/4 4-16 Ope rati onal Lea kage.....................................

3/4 4-17 3/4.4.7 CHEMISTRY...............................................

3/4 4-19 3/4.4.8 SPECIFIC ACTIVITY.......................................

3/4 4-22 3/4.4.9 PRESSURE / TEMPERATURE LIMITS Reactor Coolant System..................................

3/4 4-26 Pressurizer.............................................

3/4 4-30 Overpressure Protection Systems........................

3/4 4-31 3/4.4.10 STRUCTURAL INTEGRITY ASME Code Class 1, 2 and 3 Components...................

3/4 4-33 3/4.4.11 REACTOR VESSEL HEAD VENT................................

3/4 A-36 l

3/4.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) i i

3/4.5.1 ACCUMULATORS............................................

3/4 5-1 3/4.5.2 ECCS SUBSYSTEMS - T,yg 2 350*F..........................

3/4 5-3 3/4.5.3 ECCS SUBSYSTEMS - T,yg < 350*F..........................

3/4 5-6 NORTH ANNA - UNIT 1 V

Amendment No. 15,if, SS,64

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENT SECTIO'N PAGE 3/4.5.4 BORON INJECTION SYSTEM Boron Injection Tank.....................................

3/4 5-7 Heat Tracing.'.............................................

3/4 5-8 3/4.5.5 REFUELING WATER STORAGE TANK.............................

3/4 5-9 s

I l

l l

l NORTH ANNA - UNIT 1 VI i

n.

INDEX BASES SECTION PAGE 3/4.3 INSTRUMENTATION 3/4.3.1 PROTECTIVE INSTRUMENTATION............................... B 3/4 3-1 3/4.3.2 ENGINEERED SAFETY FEATURE INSTRUMENTATION................ B 3/4 3-1 3/4.3.3 MONITORING INSTRUMENTATION............................... B 3 /4 3-1 3/4.4 REACTOR COOLANT SYSTEM 3 /4.4.1 REACTOR COOLANT LOOPS.................................... B 3 /4 4-1 3/4.4.2 and 3 /4.4. 3 SAFETT VALVES................................. B 3 /4 4-2 3/4.4.4 PRESSURIZER.............................................. B 3/4 4-2 3/4.4.5 STEAM GENERATORS......................................... B 3/4 4-3 3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE........................... B 3 /4 4-4 p

3/4.4.7 CHEMISTRY................................................ B 3/4 4-5 3/4.4.8 SPECIFIC ACTIVITY........................................ B 3 / 4 4-5 3/4.4.,

,RESSoRE/TEMPERiToRE t1M1TS.............................. B 3 /4 4-e 3 /4. 4.10 STRUCTURAL INTEGRITY..................................... B 3 /4 4-11 3/4.4.11 REACTOR VESSEL HEAD VENT................................. B 3/4 4-13 l

NORTH ANNA - UNIT 1 XIII Amendment No. 32,NS, 64

?

INDEX fs BASES SECTION PAGE 3/4.5 EMERGENCY CORE C00 LING SYSTEMS (ECCS) 3/4.5.1 AC CUMU LATO RS............................................... 8 3/4 5-1 3/4.5.2 and 3/4.5.3 ECCS SU85YSTENS................................

8 3/4 5-1 3/4.5.4 80RON INJECTION SY5 TEM.....................................

8 3/4 5-2 3/4.5.5 REFUELING WATER STORAGE TANK (RWST)........................

8 3/4 5-3 3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT..........................................

8 3/4 6-1 y

V 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS.........................

8 3/4 6-2 3/4.6.3 CONTAINMENT ISC LATION VA LVES................................. B 3/4 6-3 3.4/6.4 COMBUSTIBLE GAS CONTR0L......................................

8 3/4 6-4 i

3/4.6.5 $U85TM05PHERIC PRESSURE CONTROL SYSTEM.......................

B 3/4 6-4 I

l NORTH ANNA - UNIT 1 XIV Amendment No.4 8 l

INSTRUMENTATION 3/4.3.3 MONITORING INSTRUMENTATION RADIATION MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.1 The radiation monitoring instrumentation channels shown in Table 3.3-6 shall be OPERABLE with their alarm / trip setpoints within the specified limits.

APPLICABILITY: As shown in Table 3.3-6.

ACTION:

a.

With a radiation monitoring channel alarm / trip setpoint exceed-ing the value shown in Table 3.3-6, adjust the setpoint to within the limit within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months or declare the channel inoperable.

b.

With one or more radiation monitoring channels inoperable, take the ACTION shown in Table 3.3-6.

c.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.3.3.1 Each radiation monitoring instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations during the modes and at the frequencies shown in Table 4.3-3.

NORTH ANNA - UNIT 1 3/4 3,35 L.

TABLE 3.3-6 RADIATION MONITORING INSTRUMENTATION 2

MINIMUM E

CHANNELS APPLICABLE ALARM / TRIP MEASUREMENT INSTRUMENT OPERABLE MODES SETPOINT RANGE ACTION E

1.

AREA MONITORS

--e a.

Fuel Storage Pool Area 1.

Criticality Monitor # 1 1 15 mR/hr 10 10+I R/hr 19 b.

Containment 1.

Purge & Exhaust Isolation 1

6

< 50 mR/hr 10 10+I R/hr 22

11. High Range Area 2

1,2,3,&4

_ 1.6x10+# R/hr 100 - 10+7 R/hr 35 w1 2.

PROCESS MONITORS w

d,

a. Ventilation Vent #

1.

Gaseous Gross Activity 1 1 x 10-5 uti/ml 10

- 10 cpm 21 6

11.

Particulate Gross 1

Activity 1

1 2 x 10-9 pC1/mi 10

- 10 cpm 21 6

b.

Containment 1.

Gaseous Activity a) Purge & Exhaust k

Isolation 1

6 1 3.6 x 10 cpm 10

- 10 cpm 22 3

6 g

b)RCS Leakage Detection 1 1, 2, 3 & 4 N/A 10

- 10 cpm 20 l

11. Particulate Activity a) Purge & Exhaust

<+

g Isolation 1

6 1 1 x 10 cpm 10

- 10 cpm 22 5

6 b)RCS Leakage Detection 1 1, 2, 3 & 4 N/A 10

- 10 cpm 20

,=

With fuel in the storage pool or building

- With irradiated fuel in the storage pool

Common to Unit 1 and Unit 2 e#

TABLE 3.3-6 (continued)

~

RADIATION MONITORING INSTRUMENTATION u

MINIMUM CHANNELS APPLICABLE ALARM / TRIP MEASUREMENT f

INSTRUMENT OPERABLE MODES SETPOINT RANGE ACTION E

2. PROCESS MONITORS (Cont'd) m c.

Noble Gas High Range Effluent Monitors

1. Ventilation Vent #

1 1,2,3, & 4 Hi 5x102 5x10-7-10+5 ci/cc 35 p

Hi Hi 103

11. Process Vent i l

1,2,3, &'4 Hi 5x104 5x10-7-10+5pC1/cc 35 Hi Hi 105 iii. Main Steam ##

1/ loop 1,2,3, & 4 Hi.26 mr/hr 10-2-10+7 mr/hr 35 Hi Hi 5.14 mr/hr w

h iv. Auxiliary Feedwater Pump Turbine Exhaust 1

1,2,3, & 4 Hi 0.2 mr/hr 10-2_10+7 mr/hr 35 Hi Hi 4.03 mr/hr F

Common to Unit 1 and Unit 2.

R

1. Main steam release path includes safety valves, atmospheric steam dump valves and the decay heat release path.

g

TABLE 3.3-6 (Continued)

TABLE NOTATION ACTION 19 -

With the number of channels OPERABLE less than -

required by the Minimum Channels OPERABLE requirement, perform area surveys of the monitored area with portable monitoring instrumentation at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

ACTION 20 -

With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE require-ment, comply with the ACTION requirements of Specification 3.4.6.1.

ACTION 21 -

With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, comply with the ACTION requirements of Specification 3.9.'12; ACTION 22 -

With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, comply with the ACTION requirements of Specification 3.9.9.

ACTION 35 -

With the number of OPERABLE channels less than required by the Minimum Channels OPERABLE requirement, either restore the inoperable channel (s) to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , or:

1.

Initiate the preplanned alternate method of monitoring the appropriate parameter (s), and 2.

Prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next 14 days following the event outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the system to 0PERABLE status.

NORTH ANNA - UNIT 1 3/4 3-37 Amendment No. 64

q c

TABLE 4.3-3 j

RADIATION MONITORING INSTRtMENTATION SURVEILLANCE REQUIREENTS Y

E CHANNEL MODES IN WHICH CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE 5

INSTRUMENT CHECK CALIBRATION TEST REQUIRED h

1.

AREA MONITORS

[

a.

Fuel Storage Pool Area 1.

Criticality Monitor #

S R

M b.

Containment 1.

Purge & Exhaust Isolation S

R M

6 11.

High Range Area S

R M

1, 2, 3, & 4 l

2.

PROCESS MONITORS a.

Ventilation Vent #

i.

Gaseous Gross Y

M Activity S

R M

11.

Particulate Gross Activity S

R M

b.

Containment 1.

Gaseous Activity a) Purge & Exhaust Isolation S

R M

6 g

b)RCS Leakage Detection S

R M

1, 2, 3, & 4

=

11.

Particulate Activity E

a) Purge & Exhaust Isolation S

R M

6 5

b)RCS Leakage Detection S

R M

1,2,3,&4 seP

With fuel in the storage pool or building g

- With irradiated fuel in the storage pool

Consnon to Unit 1 and Unit 2 o

e G

E

T TABLE 4.3-3 (Continued)

~

RADIATION MONITORING INSTRUENTATION SURVEILLANCE REQUIREMENTS 2

2 CHANNEL MODES IN WHICH E

CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE g

INSTRUMENT CHECK CALIBRATION TEST REQUIRED z

7 2.

PROCESS MONITORS (Cont'd)

E c) Noble Gas High Range Q

Effluent Monitors

1. Ventilation Vent i S

R M

1,2,3 & 4

11. Process Vent #

S R

M 1,2,3 & 4 111. Main Steaci ##

5 R

M 1,2,3 & 4 iv. Auxiliary Feedwater Pump Turbine Exhaust S

R M

1,2,3 & 4 R.

w li g

Conunon to Unit 1 and Unit 2.

1. Main steam release path includes the safety valves, atmospheric steam dump valves, and the m"

decay heat release path.

INSTRUMENTATION ACCIDENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.6 The accident monitoring instrumentation channels shown in Table l

3.3-10 shall be OPERABLE.

APPLICABILITY: MODES 1, 2 and 3.

ACTION:

a.

With the number of OPERABLE accident monitoring channels less than the total number of channels shown in Table 3.3-10, either restore the inoperable channel (s) to OPERABLE status within 7 days or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

b.

With the number of OPERABLE accident monitoring instrumentation channels less than the MINIMUM CHANNELS OPERABLE requirements of Table 3.3-10, either restore the inoperable channel (s) to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

c.

The provisions of Specification 3.0.4 are not applicable.

i SURVEILLANCE REQUIREMENTS 4.3.3.6 Each accident monitoring instrumentation channel shall be demonstrated i

OPERABLE by perfonnance of the CHANNEL CHECK and CHANNEL CALIBRATION operations at the frequencies shown in Table 4.3-7.

NORTH ANNA - UNIT 1 3/4 3-49 Amendment No. 64

o

.s TABLE 3.3-10 g

ACCIDENT MONITORING INSTRUMENTATION

' s R

TOTAL NO.

MINIMUM.

s GF CHANNELS

~

CHANNELS OPERABLE

~

c5 1.

Containment Pressure-2 1

l 2.

Reactor Coolant Inlet Temperature-Thot (wide range) 2

-1 w

3.

Reactor Coolant Inlet Temperature-Tcold (wide range) 2 1

4.

Reactor Coolant Pressure-Wide Range 1

1 5.

Pressurizer Water Level 1

1 L

6.

Steam Line Pressure 2/ steam generator 1/ steam gene'rator i

to l

in 7.

Steam Generator Water Level-Narrow Range 2/ steam generator 1/ steam generator L

8.

Refueling Water Storage Tank Water Level.

1 1

9.

Boric Acid Tank Solution Level 1

1

10. Auxiliary Feedwater Flow Rate 1/ steam generator 1/ steam generator a

11. Reactor Coolant System Subcooling Margin Monitor 2

1 2a

12. PORY Position Indicator 2/ valve 1/ valve

13. PORY Block Valve Position Indicator 1/ valve 1/ val;ve

14. Safety Valve Position Indicator 1/ valve 1/ valve T

15.

Reactor Vessel Coolant Lbvel Monitor 2

1 16.

Containment Water Level (narrow range) 2 1

17. Containment Water Level (wide range) 2 1

9

-4 TABIE 4.3-7

,i

.Es ACCIDENT MONITORING INSTRUMENTATION SURVEILIANCE REQUIREMENTS

~

\\

e t-e CHANNEL CHANNEL g

INSTRUMENT CHECK CALIBRATION 1.

Containment Pressure M

R 2.

Reactor Coolant Inlet Temperature-Thot (wi e range)

R 3.

Reactor Coolant Inlet Temperature-Teold (wide range)

M R

4.

Reactor Coolant Pressure-Wide Range M

R 5.

Pressurizer Water Level M

R 6.

Steam Line Pressure M

R 7.

Steam Generator Water Level-Narrow Range M

R N

8.

Refueling Water Storage Tank Water Level M

R Y

l0 9.

Boric Acid Tank Solution Level M

R 10.

Auxiliary Feedwater Flow Rate M

R 11.

Reactor Coolant System Subcooling Margin Monitor M

R y

12.

PORV Position Indicator M

R Eg 13.

PORV Block Valve Position Indicator M

R 14.

Safety Valve Position Indicator M

R ii 15.

Reactor Vessel Coolant level Monitor M

R

{

16. Containment Water Level (narrow range)

M R

17. Containment Water Level (wise range)

M R

3

e i

INSTRUMENTATION FIRE DETECTION INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.7 As a minimum, the fire detection instrumentation for each fire detection zone shown in Table 3.3-11 shall be OPERABLE.-

APPLICABILITY: Whenever equipment in that fire detection zone is required to be OPERABLE.

ACTION:

With one or more of the fire detection instrument (s) shown in Table 3.3-11 inoperable:

Within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months establish a fire watch patrol to inspect the a.

zone (s) with the inoperable instrument (s) at least once per hour, and b.. Restore the inoperable instrument (s) to OPERABLE status within 14 days or prepare and submit a Special Report to the Comission pursuant to Specification 6.9.2 within the next 30 days outlining the action taken, the cause of the inoperability and the plans 3

and schedule for restoring the instrument (s) to OPERABLE status, i

c.

The provisions of Specifications 3.0.3 and 3.0.4-are not applicable.

S6RVEILLANCE REQUIREMENTS 4.3.3.7.1 Each of the above required fire detection instruments shall be demonstrated OPERABLE at least once per 6 months by performance of a CHANNEL FUNCTIONAL TEST.

4.3.3.7.2 The NFPA Code 72D supervised circuits supervision associated with the detector alarms of each of the above required fire detection instruments shall be demonstrated OPERABLE at least once per 6 months.

4.3.3.7.3 The non-supervised circuits between the local panels in Specifi-l cation 4.3.3.7.2 and the control room shall be demonstrated OPERABLE at least once per 31 days.

NORTH ANNA - UNIT 1 3/4 3-52 Amendment No. 3, M,63

REACTOR COOLANT SYSTEM 3/4.4.11 REACTOR VESSEL HEAD VENT LIMITING CONDITION FOR OPERATION 3.4.11.1 At least two Reactor Vessel Head Vent (RVHV) paths consisting of two isolation valves powered from emergency buses shall be OPERABLE and closed.

APPLICABILITY: MODES 1, 2 and 3.

ACTION:

a.

With one of the above RVHV paths inoperable, startup and/or power operation may continue provided the inoperable vent path is maintained closed with power removed from the valve actuator of both isolation valves in the inoperable vent path, b.

With two RVHV paths inoperable, maintain the inoperable vent paths closed with power removed from the valve actuators of all the isolation valves in the inoperable vent paths, and restore at least one of the vent paths to OPERABLE status within 30 days or be in HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

c.

If any RVHV isolation valve cannot be verified to be closed i

within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , be in HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE REQUIREMEhTS 4.4.11.1 Each RVHV path isolation valve not required to be closed above shall be demonstrated OPERABLE by:

i j

a.

Exercising each remotely controlled valve through one cycle from the control room pursuant to Specification 4.0.5.

4.4.11.2 Each RVHV path shall be demonstrated OPERABLE following each l

refueling by:

l a.

Verifying that the upstream manual isolation valve is locked in the opened position.

b.

Verifying flow through the RVHV paths during system venting.

NORTH ANNA - UNIT 1 3/4 4-36 Amendment No. 64 i

,n,

CONTAINMENT SYSTEMS 3/4.6.4 COMBUSTIBLE GAS CONTROL HYDR 0 GEN ANALYZERS LIMITING CONDITION FOR OPERATION 3.6.4.1 Two independent containment hydrogen analyzers (shared with Unit 2) shall be OPERABLE.

APPLICABILITY: MODES 1 and 2.

ACTION:

a.

With one hydrogen analyzer inoperable, restore the inoperable l

analyzer to OPERABLE status within 30 days or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , b.

With both hydrogen analyzers inoperable, restore at least one analyzer to OPERABLE status within 7 days or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

NOTE: OPERABILITY of the hydrogen analyzers includes OPERABILITY of the respective Heat Tracing System.

SURVEILLANCE REQUIREMENTS 4.6.4.1 Each hydrogen analyzer shall be demonstrated OPERABLE at least once per 92 days on a STAGGERED TEST BASIS by performing a CHANNEL CALIBRATION using sample gas containing:

One volume percent (+.25%) hydrogen, balance nitrogen, and a.

b.

Four volume percent (+.25%) hydrogen, balance nitrogen.

NOTE: The Channel Calibration Test shall include startup and operation of the Heat Tracing System.

NORTH ANNA - UNIT 1 3/4 6-33 Amendment No. 76,64 i.

i

'C CONTAINMENT SYSTEMS i

ELECTRIC HYDROGEN RECOMBINERS LIMITING CONDITION FOR OPERATION 3.6.4.2 Two separate and independent containment hydrogen recombiner systems (shared with Unit 2) shall be OPERABLE.

APPLICABILITY: MODES 1 and 2.

ACTION:

With one hydrogen recombiner system inoperable, restore the inoperable system to OPERABLE status within 30 days or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

SURVEILLANCE REQUIREMENTS 4.6.4.2 Each hydrogen recombiner system shall be demonstrated OPERABLE:

1 At least once per 6 months by verifying during a recombiner a.

system functional test that the minimum heater sheath tem-perature. increases to > 700*F within 90 minutes and is main-tained for at least 2 Eours and that each purge blower operates for 15 minutes.

b.

At least once per 18 months by:

1.

Performing a CHANNEL CALIBRATION of all recombiner instru-mentation and control circuits.

l 2.

Verifying through a visual examination that there is no evidence of abnormal conditions within the recombiner (i.e., loose wiring or structural connections, deposits of foreign materials, etc.).

3.

Verifying during a recombiner system functional test using containment atmospheric air at a flow rate of > 50 scfm; that the heater temperature increases to > 1106'F within 5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months and is maintained for at least 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

4.

Verifying the integrity of all heater electrical circuits by performing a continuity and resistance to ground test following the above required functional test. The resistance to ground for any heater phase shall be > 10,000 ohms.

NORTH ANNA - UNIT 1 3/4 6-34

.. -.. ~

- - -, =,. -.

REACTOR COOLANT SYSTEM BASES l

3/4.4.11 REACTOR VESSEL HEAD VENT The accumulation of non-condensible gases in the Reactor CoolanY System may result from sudden system depressurization, accumulator discharges and/or inadequate core cooling conditions. The function of the Reactor Vessel Head Vent (RVHV) is to remove non-condensible gases from the reactor vessel head. The RVHV is designed with redundant safety grade vent paths.

Venting of non-condensible gases from the pressurizer steam space is provided primarily through the Pressurizer PORVs. The pressurizer is, however, equipped with a steam space vent designed with redundant safety grade vent paths.

s

-'s NORTH ANNA - UNIT 1 B 3/4 4-13 Amendment No. 64

d UNITED STATES

[.

g NUCLEAR REGULATORY COMMISSION l T' :, 5 rj WASHINGTON, D. C. 20555

\\...../

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. 49 License No. NPF-7 1.

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

A.

The application for amendment by Virginia Electric and Power Company, et al., (the licensee) dated June 3 as supplemented June 9, 1983, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application,

'the provisions of the Act, and the rules and regulations of the Comission; C.

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

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

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

0

- - - - - -,+

w,.,.

--.-.--..,,--..,-.--n-

,..--.,-,.,.,,.,,_-n---,,,--,_,-,

. 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:

(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 49, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective within 7 days from the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION kb a

Edward J. Butcher, Acting Chief Operating Reactors Branch #3 Division of Licensing

Attachment:

Changes to the Technical Specifications Date of Issuance: June 28, 1985

l ATTACHMENT TO LICENSE AMENDMENT NO.49 TO FACILITY OPERATING LICENSE NO. NPF-7 DOCKET NO. 50-339 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 vertical lines indicating the area of change.

The corresponding overleaf pages are also provided to maintain document completeness.

Page V

XI 3/4 3-39a 3/4 3-40 3/4 3-41 3/4 3-41a 3/4 3-42 (unchanged)

Y.

3/4 3-47 3/4 3-48 1

3/4 4-34 3/4 6-32 8 3/4 4-17

T INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS i

SECTION PAGE 3/4.4.2 SAFETY VALVES - SHUTDOWN............................. 3/4 4-6 3/4.4.3 SAFETY RELIEF VALVES - OPERATING

[

Safety Valves........................................ 3/4 4-7 Rel i e f Va l ves........................................ 3/ 4 4-7a 3/4.4.4 PRESSURIZER.......................................... 3/4 4-8 3/4.4.5 STEAM GENERATORS..................................... 3/4 4-9 3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE Leakage Detection Systems............................ 3/4 4-16 Operational Leakage.................................. 3/4 4-17 3/4.4.7 CHEMISTRY............................................ 3/4 4-19 3/4.4.8 SPECIFIC ACTIVITY.................................... 3/4 4-22 3/4.4.9 PRESSURE / TEMPERATURE LIMITS Reactor Cool ant Sys tem............................... 3/4 4-29 Pressurizer.......................................... 3/4 4-30 Overpressure Protection Systems...................... 3/4 4-31 3/4.4.10 STRUCTURAL INTEGRITY ASME Code Class 1, 2 and 3 Components................ 3/4 4-32 3/4.4.11 REACTOR VESSEL HEAD VENT............................. 3/4 4-34 l

i3/4.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 3/4.5.1 AC CUMU LATO RS......................................... 3/4 5-1 3/4 5.2 ECCS SUBSYSTEMS - Tavg,350*F....................... 3/4 5-3 y

3/4.5.3 ECCS SUBSYSTEMS - Tavg < 350*F....................... 3/4 5-6 3/4.5.4 BORON INJECTION SYSTEM Boron Inj ecti on Tank................................. 3/4 5-8 Heat Tracing......................................... 3/4 5-9 3/4.5.5 REFUELING WATER STORAGE TANK......................... 3/4 5-10 NORTH ANNA - UNIT 2 V

Amendment No M, 49

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 CONTAINMENT Containment Integrity.....................................

3/4 6-1 Containment Leakage.......................................

3/4 6-2 Containment Air Locks.....................................

3/4 6-4 Internal Pressure.........................................

3/4 6-6 A i r T empe ra t u re. a..........................................

3/4 6-8 Containment Structural Integrity..........................

3/4 6-9 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS Containment Quench Spray System...........................

3/4 6-10 Containment Recirculation Spray System....................

3/4 6-11,

Chemical Addition System..................................

3/4 6-13 3/4.6.3 CONTAINMENT ISOLATION VALVES..............................

3/4 6-14 3/4.6.4 COMBUSTIBLE GAS CONTROL Hydrogen Analyzers.........................................

3/4 6-32 Electric Hydrogen Recombiners.............................

3/4 6-33 Waste Gas Charcoal Filter System..........................

3/4 6-34 3/4.6.5 SUBATHOSPHERIC PRESSURE CONTROL SYSTEM Steam Jet Air Ejector.....................................

3/4 6-36 4

NORTH ANNA - UNIT 2 VI

f INDEX BASES SECTION

,- PAGE 3/4.3 INSTRUMENTATION 3/4.3.1 and 3/4.3.2 PROTECTIVE AND ENGINEERED SAFETY FEATURES (ESF) INSTRUMENTATION..............

B 3/4 3-1 3/4.3.3 MONITORING INSTRUMENTATION...............................

B 3/4 3-1 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 REACTOR COOLANT LOOPS AND COOLANT CIRCULATION............

B 3/4 4-1 3/4.4.2 and 3/4.4.3 SAFETY AND RELIEF VALVES.....................

B 3/4 4-2 3/4.4.4 PRESSURIZER..............................................

8 3/4 4-2 3/4.4.5 STEAM GENERATORS.........................................

B 3/4 4-3 3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE...........................

B 3/4 4-4 3/4.4.7 CHEMISTRY................................................

B 3/4 4-5 3/4.4.8 SPECIFIC ACTIVITY........................................

B 3/4 4-5 3/4.4.9 PRESSURE / TEMPERATURE LIMITS..............................

B 3/4 4-6 3/4.4.10 STRUCTURAL INTEGRITY....................................

B 3/4 4-16 3/4.4.11 REACTOR VESSEL HEAD VENT...............................

B 3/4 4-17 l

NORTH ANNA - UNIT 2 XI Amendment No. 49

O 4

P INDEX BASES SECTION PAGE 3/4.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 3/4.5.1 ACCUMULATORS...............................................

B 3/4 5-1 3/4.5.2 and 3/4.5.3 ECCS SUBSYSTEMS................................

B 3/4 5-1 3/4.5.4 BORON INJECTION SXSTEM.....................................

B 3/4 5-2 3/4.5.5 REFUELING WATER STORAGE TANK (RWST)........................

B 3/4 5-3 m

3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT..........................................

8 3/4 6-1 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS.........................

B 3/4 6-3 3/4.6.3 CONTAINMENT ISOLATION VALVES.................................

8 3/4 6-3 3.4/6.4 COMBUSTIBLE GAS C0NTROL......................................

B 3/4 6-4 3/4.6.5 SUBSTMOSPNERIC PRESSURE CONTROL SYSTEM.......................

B 3/4 6-4 NORTH ANNA - UNIT 2 XII

e a

TABLE 3.3-6 RADIATION MONITORING INSTRUENTATION g

MINIMUM z

CHANNELS APPLICABLE ALARM / TRIP MEASUREMENT 7

INSTRUMENT OPERABLE MODES SETPOINT RANGE ACTION E

1.

AREA MONITORS 3

ro a.

Fuel storage Pool Area Criticality Monitor i 1

1 15 mR/hr 10'4 - 10 *I R/hr 22 b.

Containment

i. Purge & Exhaust 1 50 mR/

10'4 - 10 R/hr 25 Isolation 1

6 11.6x10gR/hr

11. High Range Area 2

1,2,3, & 4 0

10

- 10+ R/hr 35 5

2.

PROCESS MDMITORS Yg a.

Ventilation Vent #

i. Gaseous Gross

< 1 x 10-5 C1/ml 10 - 10 cpm 24 6

Activity 1

11. Particulate Gross

~~

< 2 x 10'9 pC1/ml 10 - 10 cpm 24 6

Activity 1

b.

Containment

i. Gaseous Activity y

a) Purge & Exhaust 3

6 g

Isolation 1

6

< 3.6 x 10 cpm 10 - 10 cpm 25 b) RCS Leakage a

6 Detection 1

1,2,3, & 4 N/A 10 - 10 cpm 23 g

11. Particulate Activity a) Purge & Exhaust 5

6 Isolation 1

6

< 1 x 10 cpm 10 - 10 cpm 25 b) RCS Leakage 6

Dctection 1

1,2,3, & 4 N/A 10 - 10 cpm 23

With fuel in the storage pool or building

- With irradiated fuel in the storage pool

Common to Unit 1 and Unit 2 e

TABLE 3.3-6 (Continued)

Eg RADIATION MONITORING INSTRUMENTATION i

g MINIPUt g

CHANNELS APPLICABLE ALARM / TRIP MEASUREMENT INSTRUMENT OPERABLE MODES SETPOINT RANGE ACTION 2.

PROCESS MONITORS (cont'd) m c.

Noble Gas High Range Effluent Monitors 1.

Ventilation Vent #

1 1,2,3, & 4 Hi5x10h.

5x10-7-10+5 pC1/cc 35 Hi Hi 103

11. Process Vent #

1 1,2,3, & 4 Hi 5x104 5x10-7-10+5 uCi/cc 35 1

5 Hi Hi 10

".g 111. Main Steam ##

1/ loop 1,2,3, & 4 Hi.26 mr/hr 10-2-10+7 Mr/hr 35

~

Hi Hi 5.14 mr/hr iv. Auxiliary Feedwater Pump Turbine Exhaust 1

1,2,3, & 4 Hi 0.2 mr/hr 10'2-10+7 mr/hr 35 g

Hi Hi 4.03 mr/hr i

l I

E E

f Common to Unit 1 and Unit 2.

1. Main steam release path includes safety valves, atmaspheric steam dump valves and the decay heat

=*

release path.

i e

i l

1 3

1 1

TABLE 3.3-6 (Continued)

TABLE NOTATION ACTION 22 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, perform area surveys of the monitored area with portable.

monitoring instrumentation at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

ACTION 23 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, comply with the ACTION requirements of Specification 3.4.6.1.

ACTION 24 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, comply with the ACTION requirements of Specification 3.9.12.

ACTION 25 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, comply with the ACTION requirements of Specification 3.9.9.

ACTION 35 With the number of OPERABLE channels less than required by the Minimum Channels OPERABLE requirement, either restore the inoperable channel (s) to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , or:

1.

Initiate the preplanned alternate method of monitoringtheappropriateparameter(s),and 2.

Prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next 14 days following the event outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the system to OPERABLE status.

NORTH ANNA - UNIT 2 3/4 3-40 Amendment No. 49

TABLE 4.3-3 g

RADIATION MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL MODES IN WHICH g

~ CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE g

INSTRUMENT CHECK CALIBRATION TEST REQUIRED h

1.

AREA MONITORS U

a.

Fuel Storage Pool Area N

Criticality Monitor #

S R

M b.

Containment v

1.

Purge & Exhaust Isolation S

R M

6

11. High Range Area S

R M

1, 2, 3, & 4 g

2.

PROCESS MONITORS y

a.

Ventilation Vent #

f:

1.

Gaseous Gross Activity S

R M

11. Particulate Gross Activity S

R M

b.

Contairurent

i. Gaseous Activity k

a) Purge & Exhaust k'

Isolation S

R M

6 b) RCS Leakage Detection S

R M

1, 2, 3, & 4 5

11. Particulate Activity

=

P a) Purge & Exhaust Isolation S

R M

'6 b) RCS Leakage Detection S

R M

1, 2, 3, & 4

With fuel in the storage pool or building

- With irradiated fuel in the storage pool

Common to Unit 1 and Unit 2 J

TABLE 4.3-3 (Continued)

RADIATION MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS

];

CHANNEL MODES IN WHICH j;

CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE INSTRUMENT

_ CHECK CALIBRATION TEST REQUIRED f

2.

PROCESS MONITORS (Cont'd) c) Noble Gas High Range m

Effluent Monitors 1.

Ventilation Vent i S

R M

1, 2, 3, & 4

11. Process Vent #

5 R

M 1, 2, 3, & 4 iii. Main Steam ##

S R

M 1, 2, 3, & 4 iv. Auxiliary Feedwater Pump u,

Turbine Exhaust S

R M

1, 2, 3, & 4 1

u, b

=

F

.i A

.E e

'i f Comon to Unit 1 and Unit 2.

1. Main steam release path includes the safety valves, atmospheric steam dump valves, and the decay heat release path.

C INSTRUMENTATION MOVABLE INCORE DETECTORS LIMITING CONDITION FOR OPERATION 3.3.3.2 The movable incore detection system shall shall be OPERABLE with:

a.

At least 75% of the detector thembles, b.

A minimum of 2 detector thimbles per core quadrant, and SufficientmovIbledetectors, drives,andreadoutequipmentto c.

map these thimbles.

APPLICABILITY:

When the movable incore detection system is used for:

a.

Recalibration of the ecore neutron flux detection system, b.

Monitoring the Quadrant POWER TILT RATIO, or MeasurementofFh,F(Z)andFxy (Z) c.

q ACTION:

With.the movable incore detection system inoperable, do not use the system for the above applicable monitoring or calibration functions.

The provi-sions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.3.3.2 The movable incore detection system shall be demonstrated OPERABLE, at least once per 24' hours, by normalizing each detector output to be used during its use when required for:

a.

Recalibration of the excore neutron flux detection system, or b.

Monitoring the QUADRANT POWER TILT RATIO, or MeasurementofFfH,F(Z)andFxy (Z) c.

q NORTH ANNA - UNIT 2 3/4 3-42

TABLE 3.3-10 z

ACCIDENT MONITORING INSTRUMENTATION 2,

TOTAL NO.

MINIMUM OF CHANNELS

{

CHANNELS OPERA 8LE E

1.

Containment Pressure 2

1 2.

Reactor Coolant Outlet Temperature-That (wide ra g )

2 1

m 3.

Reactor Coolant Inlet Temperature-Teold (wide' range) 2 1

4 Reactor Coolant Pressure-Wide Range 1

1 5.

Pressurizer Water Level 1

1 6.

Steam Line Pressure 2/ steam generator 1/ steam generator 7.

Steam Generator Water Level-Marrow Range 2/ steam generator 1/ steam generator 8.

Refueling Water Storage Tank Water Level 1

1 9.

Boric Acid Tank Solution Level 1

1 10.

Auxiliary Feedwater Flow Rate 1/ steam generator 1/ steam generator g

Reactor Coolant System Subcooling Margin Monitor 2

1 11.

R 12.

PORY Position Indicator 2/ valve 1/ valve

~

=

13.

PORV Block Valve Position Indicator 1/ valve 1/ valve

,E 14.

Safety Valve Position Indicator 1/ valve 1/vgive g

f5.

Reactor Vessel Coolant Level Monitor 2

1 16.

Containment Water Level (narrow range) 2 1

17.

Containment Water Level (wide range) 2 1

TABLE 4.3-7 ACCIDENT MNIITORING INST M NTATION SURVEILLANCE REQUIREMENTS E

CHANNEL CHANNEL INST M NT CHfCK CALIBRATION E

1.

Containment Pressure M

R

=

2.

Reactor Coolant Outlet Temperature-T I"Id' "*"9')

M E

hot 3.

Reactor Coolant Inlet Temperature-T I"

- * )

N E

cold 4.

Reactor Coolant Pressure-Wide Range M

R 5.

Pressurizer Water Level M

R 6.

Steam Line Pressure M

R 7.

Steam Generator Water Level-Marrow Range M

R 1

8.

Refueling Water Storage Tank Water Level M

R 9.

Boric Acid Tank Solution Level M

R 10.

Auxiliary Feedwater Flow Rate M

R 11.

Reactor Coolant System Subcooling Margin Monitor M

R k

12.

PORY Position Indicator M

R Rg 13.

PORV Block Valve Position Indicator M

R f

14.

Safety Valve Position Indicator M

R g

15.

Reactor Vessel Coolant Level Monitor M

g 16.

Containment Water Level (narrow range)

M R

17.

Containment Water Level (wide range)

M R

1 REACTOR COOLANT SYSTEM 3/4.4.11 REACTOR VESSEL HEAD VENT LIMITING CONDITION FOR OPERATION 3.4.11.1 At least two Reactor Vessel Head Vent (RVHV) paths consisting of two isolation valves powered from emergency buses shall be OPERABLE and closed.

APPLICABILITY: MODES 1, 2 and 3.

ACTION:

a.

With one of the above RVHV paths inoperable, startup and/or power operation may continue provided the inoperable vent path is maintained closed with power removed from the valve actuator of both iso 13 tion valves in the inoperable vent path, b.

With two RVHV paths inoperable, maintain the inoperable vent paths closed with power removed from the valve actuators of all the isolation valves in the inoperable vent paths, and restore at least one of the vent paths to OPERALLE status within 30 days or be in HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

c.

If any RVHV isolation valve cannot be verified to be closed within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , be in HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE REQUIREMENTS 4.4.11.1 Each RVHV path isolation valve not required to be closed above shall be demonstrated OPERABLE by:

a.

Exercising each remotely controlled valve through one cycle from the control roorn pursuant to Specification 4.0.5.

4.4.11.2 Each RVHV path shall be demonstrated OPERABLE following each refueling by:

a.

Verifying that the upstream manual isolation valve is locked in the opened position, b.

Verifying flow through the RVHV paths during system venting.

NORTH ANNA - UNIT 2 3/4 4-34 Amendment No. 49

m

.,..o e

C CONTAINMENT SYSTEMS 3/4.6.4 COMBUSTIBLE GAS CONTROL HYDROGEN ANALYZERS LIMITING CONDITION FOR OPERATION 3.6.4.1 Two independent containment hydrogen analyzers (shared with Unit 1) shall be OPERABLE.

APPLICABILITY: MODES 1 and 2.

ACTION:

With one hydrogen analyzer inoperable, restore the inoperable a.

i analyzer to OPERABLE status within 30 days or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , b.

With both hydrogen analyzers inoperable, restore at least one analyzer to OPERABLE status within 7 days or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

NOTE: OPERABILITY of the hydrogen analyzers includes OPERABILITY of the respective Heat Tracing System.

SURVEILLANCE REQUIREMENTS 4.6.4.1 Each hydrogen analyzer shall be demonstrated OPERABLE at least once per 92 days on a STAGGERED TEST 8 ASIS by performing a CHANNEL CALIBRA-TION using sample gas containing:

One volume percent (1 25%) hydrogen, balance nitrogen, and a.

b.

Four volume percent (1 25%) hydrogen, balance nitrogen.

NOTE: The Channel Calibration Test shall include startup and operation of the Heat Tracing System.

NORTH ANNA - UNIT 2 3/4 6-32 Amendment No. 25, 49

REACTOR COOLANT SYSTEM BASES 3/4.4.11 REACTOR VESSEL HEAD VENT The accumulation of non-condensible gases in the Reactor Coolant System may result from sudden system depressurization, accumulator discharges and/or inadequate core cooling conditions. The function of the Reactor Vessel HeadVent(RVHV)istoremovenon-condensiblegasesfromthereactorvessel head. The RVHV is designed with redundant safety grade vent paths.

Venting of non-condensible gases from the pressurizer steam space is provided primarily through the Pressurizer PORVs. The pressurizer is, however, equipped with a steam space vent designed with redundant safety grade vent paths.

NORTH ANNA - UNIT 2 B 3/4 4-17 Amendment No. $9, 49

-

ML20132F025

Text

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