Text

Amends 138 & 121 to Licenses NPF-4 & NPF-7,respectively, Revising Requirements Governing Operability of Individual Rod Position Indication (Irpi) Sys.Change Shifts Emphasis from Irpi Sys to Demand Position Indication Sys
	ML20059G337
Person / Time
Site:	North Anna
Issue date:	08/27/1990
From:	Berkow H; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20059G339	List: ML20059G337; ML20059G351;
References
	NUDOCS 9009120261
	Download: ML20059G337 (46)
	v • d • e

_

i

se Els\\o

/g UMTED STATES

{

I NUCLEAR REGULATORY COMMISSION MSmNG TON, D. C. 20%5 s

i f

...../

VIRGINIA ELECTRIC AND POWER COMPANY OLD DOMINION ELECTRIC COOPERATIVE i

DOCKET NO. 50-338 NORTH ANNA POWER STATION. UNIT NO. I t

AMENDMENT TO FACILITY OPERATING LICENSE

. Amendment No. 138 License No. NPF 1 1.

The Nuclear Regulatory 20 mis-ion (the Comission) has found that:

A.

The application for amendment by Virginia Electric and Power Company etal.,(thelicensee)datedApril 30, 1990, 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 Commission; 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 1

conducted in compliance with the Comission's regulations; D.

The issuana 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.

f I

{

l-I 1

9009120261 900827

)

ADOCK 0 % g 8 j

DR a

~

is 2.

Accordingly, the license is amended by changes to the Technical Speci-fications 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 The Technical Specifications contained in Appendices A and B, as revised through Amendment No.138, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

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

FOR T NUCLEAR REGULATORY COMMISSION lHerbertN.Berkow, Director Project Directorate II Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Spepifications Date of Issuance: August 27, 1990 I

l ATTACHMENT TO LICENSE AMENDMENT NO.138 10 FACILITY OPERATING LICENSE NO. NPF-4 DOCKET NO. 50-338 Replace the following pages of the Appendix "A" Technic)1 Spe:ifications with the enclosed pages as indicated. The revised pages are identified by a

amendment number and contain vertical lines indicating the area of change.

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

.P.E.9.!i X

XVI 3/4 1-18 3/4 1-19 3/4 1-21 3/4 1-21a 3/4 1-22 3/4 1-24 3/4 1-25 3/4 10-5 B 3/4 1-4 B 3/4 1-4a i

B 3/4 10-1 i

1 1

1 INDEX l

i LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS I

i I

SECTION PAGE i

l 3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1 A.C. SOURCES i

i 0perating...............................................

3/4 8-1 j

Shutdown................................................

3/4 8-5 3/4.8.2 ONSITE POWER DISTRIBUTION SYSTEMS i

A.C. Distribution - Operating...........................

3/4 8-6 e

A.C. Distribution - Shutdown............................

3/4 8 D.C. Distribution - 0ptrating...........................

3/4 8-8'

[

0.C. Distribution - Shutdown............................

3/4 8-10 5

3/4.9 REFUELING OPERATIONS 3/4.9.1 BORON CONCENTRATION.....................................

3/4 9-1 3/4.k 2 INSTRUMENTATION.........................................

3/4 9-2 3/4.9.3 DECAY TIME..............................................

3/4 9-3 3/4.S.4 CONTAINMENT BUILDING PENETRATIONS.......................

3/4 9-4 l

3/4.9.5 COMMUNICATIONS..........................................

3/4 9-5

{

3/4.9.6 MANI PULATOR CRANE OPERABILITY...........................

3/4 9-6 3/4.9.7 CRANE TRAVEL - SPENT FUEL PIT...........

3/4 9-7 3/4.9.8 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION.

{

All Water Levels........................................

3/4 9-8 Low Water Leve1.........................................

3/4 9-8a

)

3/4.9.9 CONTAINMENT PURGE AND EXHAUST ISOLATION SYSTEM..........

' 3/4 9-9 3/4.9.10 WATER LEVEL - REACTOR VESSEL............................

3/4 9-10 t

I F

NORTH ANNA - UN'.'T 1 IX Amendment No. 32 4

.-.m.--.

t l

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE l

3/4.9.11 SPENT FUEL PIT WATER LEVEL...................~..........

3/4 9-11 3/4 9.12 FUEL BUILDING VENTILATION SYSTEM.......................

3/4 9-12 3/4.10 SPECIAL TEST CXCEPTIONS 3/ 4.10.1 ' SHUT DOWN MARG I N........................................

3/4 10-1 3/4.10.2 GROUP HEIGHT INSERTION AND POWER DISTRIBUTION..........

3/4 10-2 3/4.10.3 PHYSICS TEST...........................................

3/4 10 3/4.10.4 REACTOR COOLANT L00PS..................................

3/4 10-4 2

t i

e i

L NORTH ANNA - UNIT.1 X

Amendment No. 118, e

i f

i i

INDEX i

i BASES i'

SECTION PAGE j

3/4.7 PLANT SYSTEMS i

3/4.7.1 TURBINE CYCLE.......................................

B 3/4 7-1 i

3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION.....

B 3/4 7-4 3/4.7.3 COMPONENT COOLING WATER SUBSYSTEM...................

B 3/4 7-4

+

3/4.7.4 SERVICE WATER SYSTEM................................

B 3/4 7-4

[

3/4.7.5 ULTIMATE HEAT SINK..................................

B 3/4 7-S-3/4.7.6 FLOOD PROTECT 10N....................................

B 3/4 7-5 3/4.7.7 CONTROL ROOM EMERGENCY HABITABILITY.................

B 3/4 7-5L f

3/4.7.B SAFEGUARDS AREA VENTILATION SYSTEM..................

B 3/4 7-5

)

3/4.7.9 RESIDUAL HEAT REMOVAL SYSTEMS.......................

B 3/4 7-6 3/4.7.10 H YD RAUL IC S NU B BE RS..................................

B 3/4 7-6 3/4.7.11 SEALED SOURCE CONTAMINATION.........................

B 3/4 7 1 3/4.7.12 SETTLEMENT OF CLASS 1STRUCTURES....................

B 3/4 7-7a f

l 3/4.7.13 GROUNDWATER LEVEL - SERVICE WATER RESERVOIR.........

B 3/4 7-9 l

l 3/4.7.14 FIRE SUPPRESSION SYSTEMS............................

B 3/4 7-9 1

l 3/4.7.15 PENET RATION FIRE BARRI ERS...........................

B 3/4 7-10

{

3/4.8 ELECTk! CAL POWER SYSTEMS 3/4.8.1 A.C. 50VRCES.............

.......................... B 3/4 8-1 3/4.8.2 ONSITI F0WER DISTRIBUTION SYSTEMS...................

B 3/4 8 t l

3/4.9 REFUElli.G OPERATIONS 3/4.9.1 BOR01' CONC E NT RAT I ON.................................

B 3/4 9-1 3/4.9.2 I N ST RUl iE NT AT 10 N..................................... B 3/4 9-1 NORTH ANNA - UNti i XV Amendment No. 3, 5,16

' t

~

s -

~

e

l l

i i

l 1

i INDEX 8ASES I

i 1

SECTION PAGE i

3/4.9.3 DECAV TIME..............................................

B 3/4 9-1 i

i 3/4.9.4 CONTAINMENT BUI LDING PENETRATIONS.......................

B 3/4 9-1

[

3/4.9.5 COMMUNICATIONS..........................................

B 3/4 9-1 3/4.9.6 MANIPULATOR CRANE OPERABI LITY...........................

B 3/4 9-2 l

3/4.9.7 CRANE TRAVEL - SPENT FUEL PIT...........................

B 3/4 9-2 j

3/4.9.8 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION...........

B 3/4 9-2 i

3/4.9.9 CONTAINMENT PURGE AND EXHAUST ISOLATION SYSTEM..........

3 3/4 9-2 l

3/4.9.10 and 3/4.9.11 WATER LEVEL-REACTOR VESSEL AND SPENT FUEL PIT..............................................

B 3/4 9-3 3/4.9.12 FUEL BUILDING VENTI LATION SYSTEM........................

B 3/4 9-3 3/4.10 SPECIAL TEST EXCEPTIONS 3/4'.10.1 SHUTDOWN MARGIN.........................................

B 3/4 10-1 3/4.10.2 GROUP HEIGHT INSERTION AND POWER DISTRIBUTION LIMITS................................................

B 3/4 10-1 3/4.10.3 PHYSICS TESTS...........................................

B 3/4 10-1 3/4.10.4 REACTOR COOLANT L00PS...................................

B 3/4 10-1 t

6 i

L i

l I

t t

i NORTH ANNA - UNIT 1 XVI AmendmentNo.ft.138 n-,,-.

-,--w--

a-n-,

,er.

--v

~ m e

,-e--

^

W i

l REACTIVITY CONTROL SYSTEMS i

SURVEILLANCE REQUIREMENTS (Continued) l a.

At least once per 7 days by:

1.

Verifying the boron concentration in each water souice.

2.

Verifying the contained borated water volume of each water source, and l

3.

Verifying the boric acid storage system solution temperature.

b.

At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by verifying the RWST temperature.

7 NORTH ANNA-UNIT 1 3/4 1-17 Amendnent No. 5

l l

,REACTMTY COhrTROL SYSTEMS f

3/4.1.3 MOVABLE CONTROL ASSEMBLIES GF h GGHT i

UMITING(ONDITION FOR OPERATION i

3.1.3.1 All shutdown and control rods shall be OPERABLE and positioned within t 12 steps' of their group step counter demand position.

1 i

APPLICABILITY: MODES 1" and 2".

AGIl21:

l With one or more rods Inoperable due to being iminovable as a result of excessive l

i friction or mechanical interference or known to be untrippable, determine within

.I one hour that the SHUTDOWN MARGIN requirement of Specification 3.1.1.1 is i

satisfied and be in HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

b.

With more than one rod inoperable due to causes other than those addressed.by ACTION *a" above or misaligned from the group step counter demand position by more than the above alignment requirements, determine within one hour that the

}

SHUTDOWN MARGIN requirement of Specification 3.1.1.1 is satisfied and be in HOT i

STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

I E

c.

With a maximum of one rod inoperable due to causes other than those addressed by ACTION *a' above or misaligned from the group step counter demand position by.

more than the above alignment requirements, POWER OPERATION may continue provided that within one hour, either:

1.

The rod is restored to OPERABLE status within-the above alignment requirements, or j

i 2.

The rod is declared inoperable and the SHUTDOWN MARGIN requirement of i

Specification 3.1.1.1 is satisfied. POWER OPERATION may then continue provided that:

a)

A reevaluation of each accident analysis to Table 3.11 is performed l

l within 5 days. This reevaluation shall confirm that the previous analyzed results of these accidents remain valid for the duration of I

l operation under these conditions, and l

For power levels below 50% of RATED THERMAL POWER, the position of each rod as l

determined by its individual rod position indicator may be more than i 12 steps from its group step counter demand position for a maximum of one hour in every 24. During this

[

l hour, the indicated position of each rod may be no more than 2 24 steps from its demand position. The 124 step / hour limit is not applicable when control rod position is known to be greater than 12 steps from the rod group step counter demand position indication.

See Special Test Exceptions 3.10.2 and 3.10.3.

NORTH ANNA UNIT 1 3/4 1 18 Amendment No. 76, 138 i

i 7

\\

I i

k REACTIVITY CONTROL SYSTEMS

+

LIMITING CONDITION FOR OPERATION (Continued) b)

The SHUTDOWN MARGIN requirement of Specification 3.1.1.1 is determined at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , and c)

A power distribution map is obtagned from the movable i

incoredetectorsandF(Z)andF a

withintheirlimitswikhin72ho6Ys,reverifiedtobe or d)

Either the THERMAL POWER level is reduced to < 75%

i of RATED THERMAL POWER within one hour and within the 4

next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months the high neutron flux trip setpoint is reduced to < 85% of RATED THERMAL POWER, or e)

The remainder of the rods in the group with the inoperable rod are aligned to within + 12 steps of the inoperable rod within the hour while maintain-ing the thermal power, rod sequence', and insertion limits of Specification 3.1.3.6 during subsequent operation.

SURVEILLANCE REQUIREMENTS 4.1.3.1.1 The position of each rod shall be determined-to be within the l

groups demand _ limit by verifying the individual rod positions at least 3

once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months except during time intervals'when,the Rod Position Deviatien Monit6r is inoperable, then verify the group positions at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

4.1.3.1.2 Each rod not fully inserted'in the core shall be determined to l

be OPERABLE'by movement of at least 10 steps'in any one direction at, l

least once per 31 days.

NORTH ANNA-UNIT 1 3/4 1-19 Amendment No. M.138:

l

)

TABLE 3.1-1 ACCIDENT ANALYSES REQUIRING' REEVALUATION IN THE EVENT OF AN INOPERABLE-FULL LENGTH ROD Rod Cluster Control Assembly Insertion Characteristics i

Rod Cluster Control Assembly Misalignment.

1 i

Loss of Reactor Coolant From Small Ruptured Pipes Or From Cracks In Large Pipes Which Actuates The Emergency Core Cooling System

~

Single Rod Cluster Control Assembly Withdrawal At Full Power Major Reactor Coolant System Pipe Rupture (LossOfCoolantAccident)

Major Secondary System Pipe Rupture 7

Rupture of a Control Rod Drive Mechanism Housing i

(Rod Cluster Control Assembly Ejection) e i

t i

i i

i i.

NORTH ANNA-UNIT 1 3/4 1-20 Amendment No.16 t

~

i l

\\

REACTMTYCONTROLSYSTEMS POSITIONINDICATORCHANNELS OPERATING 3

LfMITING CONDITION FOR OPERATION mm- - -

3.1.3.2 The shuttwn and control rod position indicating system shall be OPERABLE with:

Each individual rod position indicator channel,1 per rod, accurate to within ! 12 a.

steps

of actual rod position, and b.

Each demand position indicator,1 per group, accurate to within i 2 steps of demand position, and i

The Automatic Rod Position Deviation Monitor with the alarm setpoint < 12 steps, c.

l APPUCABILITY: MODES 1 and 2.

ACTION.

t' I

With a maximum of one individual rod position Indicator channel per group f

a.

inoperable, either:

Determine the position of the non. indicating rod indirectly by the movable l

1.

incore detectors at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months and immediately after any motk'1 of the non indicating rod which exceeds 24 steps in one direction since il e lam determination of the rod's position as well as verify that the rod pcsition l

requirements of Specification 3.1.3.1 are satisfied, or I

2.

Reduce THERMAL POWER to < 50% of RATED THERMAL POWER within 6 ~

hours and verity that the requirements of Specification 3.1.3.1 are satisfied.

l b.

With a maximum of one demar; 0%n indicator per bank inoperable, either:

1.

Verify that all individual rod p.

,n Indicators for the affected bank are OPERABLE and that the most witi,orawn rod and the least withdrawn rod of the bank are within a maximum of 12. steps of each other at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months , or 2.

Reduce THERMAL POWER to < 50% of RATED THERMAL POWER within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months and verify that the requirements of Specification 3.1.3.1 are satisfied.

l 1

With the Automatic Rod Position Deviation Monitor inoperable, compare the c.

demand position indicators and the individual rod position indicator channels at 1

l

.least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months to ensure that rod position indication is within the above tolerance requirements. The provisions of Specification 3.0.4 are not applicable.

t Below 50% power each individual rod position indicator may be more than i 12 steps from its group step oounter demand position for a maximum of one hour in every 24. During this hour, each individual rod position indicator may be no more than i 24 steps from its i

demand position, 11 either the one hour period or the i 24 step limit is exceeded, immediately declare the individual rod position indicator channel inoperable.

NORTH ANNA -~ UNIT 1 3/4 1-21 Amendment No. 16, 138.

1 REACTMTY CONTROLSYSTEMS POSITIONINDICATORCHANNELS OPERATING SURVElli.ANCE REQUIREMENTS 4.1.3.2.1 Each individual rod position indicator shall be determined to be OPERABLE by:

Periorming a CHANNEL CHECK

by interoomparison of each individual rod position a

indicator and its corresponding demand position indicator at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , and b.

Performing a CHANNEL FUNCTIONAL TEST and CHANNEL CAUBRATION at least once per 18. months.

4 4.1.3.2.2 'acn %av position indicator shall be determined to be OPERABLE by:

Performing a CHANNEL CHECK of the demand position indicators within a bank at a.

least once per 7 days, and ~

4 b.

Performing a CHANNEL CHECK by an intercomparison of the control bank benchboard demand position indicators and the rod control system logic cabinet bank overlap indicator or the rod position indicator cabinet P/A indicators, and determining their agreemont within 2 steps, at least once per 92 days.

4.1.3.2.3 The Automatic Rod Position Deviation Monitor shall be determined to be OP by performing a functional test of the process computer alarm to demonstrate the process computer remains capable of recognizing a deviation of 12 steps or more at least once per 7 days.

I l

i Below 50% power each individual rod position indicator may be more than 12 steps from-its group step counter demand position for a maximum of one hour in every 24. During this hour, each individual rod position indicator may be no more than 2 24 steps from its demand

- position, if either the one hour period or the 124 step limit is exceeded, immediately declare the individual rod position Indicator channel inoperable.

A scan frequency of approxima,ely once per minute, by either the plant computer or a data acquisition system, is acceptable for determining the total time that a rod is position indicator has deviated more v

than 12 steps but no more than 124.

A rod position indicator which is found to be so deviated is assumed to have been deviated for the entire scanning period. When the scanner is unavailable to sum deviated time, the tolerance reverts to i 12 steps, i

NORTH ANNA UNIT 1 3/4 1 21a Amendment No. 138, I

REACTIVITY CONTROL SYSTEMS POSITION INDICATOR CHANNELS-SHUTDOWN 1

LIMITING CONDITION FOR OPERATION

~

3.1.3.3 The rod group step counter demand position indicator shall be OPERABLE and eccurate to within + 2 steps of the demand position from the logic cabinet for each shutdown or control rod group not fully inserted.

APPLICABILITY: MODES 3*, 4*

and 5*.

ACTION:

With less than the above required demand position indicators OPERABLE, open'the reactor trip system breakers within 15 minutes, i

i i

i SURVEILLANCE REQUIREMENTS 4.1.3.3 Each of the above required demand position indicators sh&11 be determined to be OPERABLE by:

{

a.

Performing a CHANNEL CHECK of the demand position indicators i

within a bank at least once per 7 days, and b.

Performing a CHANNEL CHECK by an intercomparison of the' control bank benchboard demand position indicators and the rod control system logic cabinet bank overlap indicator or the rod position indicator cabinet P/A indicators, and determining their agreement within + 2 steps, at least once per 92 days, c.

The provisions of Specification 4.0.4 are not applicable, a

l g

With the reactor trip system breakers in the closed position.

i 1

NORTH ANNA-UNIT 1 3/4 1-22

-AmendmentNo.)$,138 l

l

t REACTIVITY CONTROL SYSTEMS ROD DROP TIME LIMITING CONDITION FOR OPERATION 3.1.3.4 The individual full length (shutdown and control) rod drop time from the fully withdrawn position shall be 1 2.2. seconds from beginning of decay of stationary gripper coil voltage to dashpot entry with:

T,yg >_ 500'F, and a.

b.

All reactor coolant pumps operating.

APPLICABILITY: MODES 1 and 2.

ACTION:

a.

With the drop time of any full length rod determined to exceed the above ~1imit, restore the rod drop time to within the above limit prior to proceeding to MODE 1 or 2.

b.

With the rod drop times within limits but determined with 2 -

reactor coolant pumps operating, operation may proceed provided THERMAL PCWER is restricted to:

1.

< 66% of RATED THERMAL POWER when the reactor coolant stop valves in the nonoperating. loop are open, or 2.

< 71% of RATED THERMAL POWER when the reactor coolant stop valves in the nonoperating loop-are closed, j

SURVEILLANCE REQUIREMENTS 4.1.3.4 The rod drop time of full length rodi hall be demonstrated through measurement prior to reactor criticality:

a.

For all rods following each removal of the reactor vessel head, b.

For specifically affected individual rods following any main-tenance on or modification to the control rod drive system which could affect the drop time of those specific rods,.and c.

At least.once per 18 months.

NORTH ANNA-UNIT 1

'3/4 1-23

_. _., ;J

REACTIVITY CONTROL SYSTEMS SHUTDOWN R0D INSERTION LIMIT LIMITING CONDITION FOR OPERATION 3.1.3.5 All shutdown rods shall be fully withdrawn.

APPLICABILITY: MODES 1* and 2*#

ACTION:

With a maximum of one shutdown rod not fully withdrawn, except for surveillance testing pursuant to Specification 4.1.3.1.2, within one hour either:

a.

Fully withdraw the rod, or b.

Declare the rod to be inoperable and apply Specification 3.1.3,1

, SURVEILLANCE REQUIREMENTS h

4.1.3.5 Each shutdown rod shall be determined to be fully withdrawn:

a.

Within 15 minutes prior to initial control rod bank withdrawal during an approach to reactor critic'lity, and-a b.

At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter.

See Special Test Exceptions 3.10.2 and 3.10.3.

With X,ff > 1,0 NORTH AN'A-UNIT 1 3/4 1-24 Amendment No. 138, N

I

REACTIVITY CONTROL SYSTEMS CONTROL ROD INSERTION LIMITS LIMITING CONDITION FOR OPERATION 3.1. 3. 6 The control banks shall be limited in physical insertion as shown in Figures 3.1-1. and 3.1-2.

APPLICABILITY: MODES 1* and 2*#.

ACTION:-

With the control banks inserted beyond the above insertion limits, except for surveillance testing pursuant to Specification 4.1.3.1.2, either:

a.

Restore the control banks to within the liniits within two hours, or b.

Reduce THERMAL POWER within two hours to less than or equal to that fraction of RATED THERMAL POWER which is allowed by the-rod group step counter demand position using the above figures, or c.

Be-in HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

SURVEILLANCE REQUIREMENTS i

4.1.3.6 The position of each control bank shall be, determined to be I

within the insertion limits at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months except during time-intervals when the Rod Insertion LimH Monitor it inoperabl0, then-verify either the individual red positions-(indicated positions) or' the group step counter demand position of each rod group to be within the insertion limits at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

See Special Test Exceptions 3.10.2 and 3.10.3.

With K,ff 1 1.0.

1 l

NORTH ANNA-UNIT 1 3/4 1-2S Amendment No.138,

i.

J I

l FULI.Y WITHDRAWN 228

.54,228)!

_.J _ _

i----b 220 c

I t

200

- 7t

-f (1,194)

+

./

BANK C

~

~ ' - ~ ~

~~-

~

180 l..

~.

..a.

.t

~I -

- - + - -

160 g

I

- "-y' - --

140

--L a.

t

~

"-- ~~ ^-

- -i -- - n

-"4-y 120 m

(0,118)

-l-r i.

a.

4.

3 t

e

'- 1 o 100 4 -- ; - -

- - *j --- -

e j

BANK D.

g

" --- 1 --

80 7 '--

- ---n--

E l

i l

l 60

+----n----

....2, I

1 40 a

.: .,.a _ ;.__

.I l

}

r 20 1--.._u..L. j i

1-.

__u

. 1_

I t

L j

i

(.048,0) 0 0

.1

.2

.3

.4 -

.5

.6

.7 -

.8

.9

- 1.0 t

FULLY INSERTED FRACTION OF RATED THERMAL POWER Figure 3.11 Rod Group Insertion Limits Versus Thermal Power-NORTH ANNA - UNIT 1 3/4 1 26

u j

l l

l

?

1 i

j I

i

?

I l

t t

i THIS PAGE DELETED -

l l

l

?

l l

i c

1 1

NORTH ANNA UNIT 1 3/4 10 5 Amendment No. 15, 138-8

. ~

REACTIVITY-CONTROL SYSTEMS BASES

.~

3/4.1.2 B0 RATION SYSTEMS (Continued)

With the RCS average temperature above 200'F, a minimum of two separate i

and redundant boron injection systems are provided to ensure single functional i

capability in the event an assumed failure renders one of the systems inoperable.

Ailowable out-of-service periods ensure that minor component repair or corrective action may be completed without undue risk to overall facility safety from injection system failures during.the repair period.

The boration capabloity of either system is sufficient to provide a SHUTDOWN MARGIN from expected operating cctditions of 1.77% ak/k after xenon decay and cooldown to 200'F. This expected boration capabil.ity requirement occurs at ECL from full power equilibrium xenon conditions and requires 6,000 gallons of 12,950 ppm borated water from the boric acid storage tanks or 54,200 gallons of 2300 ppm borated water from the rafueling water storage tank.

[

The limitation for a maximum of one centrifugal cn:rging pump to be OPERA'BLE and the Surveillance Requirement to verify all -harging pumps except j

the required OPERABLE pump to be inoperable below 324'F 1 covides assurance l

that a mass addition pressure transient can be relieved tf the operation of a single PORV.

With the RCS-temperature below 200*F, one injection _ system is acceptable l

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.

i The boron capability required below 200'F is sufficient to provide a SHUTDOM MARGIN of 1.77% ak/k after xenon decay and cooldown from 200*F to 4

140*F. This condition requires either 1378 gallons of 12.950 ppm borated water from the boric acid stc.. age tanks or 3400 gallons of 2300 ppm borated wat; from the refueling water storage tank.

The contained water volume limits include allowance for water not available because of discharge line location and other physical characteristics.

The OPERABILITY of one boron injection system during REFUELING insures that this system is available for reactivity control while in MODE -6.

NORTH ANNA - UNIT 1 B 3/4 1-3 Amendment No. 5, 76, $$,93,117

~

a l

REACTMTYCONTROLSYSTDAS uSES t

3/4.1.2 BORATION SYSTEMS (Continuedi rt The limits on contained water volume and boron concentration of the RWST also ensure a~

pH.value of between 8.5 and 11.0 for the solution. recirculated.within the containment after a LOCA. This pH minimizes the evolution of iodine and minimizes the effect of chloride and caustic stress corrosion on mechanical systems and components.

At least one chargN oump must remain operable at all times when the opposite' unit is in 4

~

MODE 1, 2. 3, or 7.

This is required to' maintain the charging pump cross connect system 3

operaticaal.

3/4.11s MOVABLE CONTROL ASSEMBLIES I

The specifications of this section (1) ensure that acceptable power distribution limits Lare maintained,,4 ensure that the minimum SHUTDOWN MARGIN is maintained,' and (3) limit the potential effects of rod misalignment:on associated accident analysesi OPERABILNY of the movable control assemblies is established by observing rod motion and determining that rods are positioned w!N 112 steps (indicated position) of the respective demand step counter position. The OPF.RABILITY of the individual rod pos! tion indication system is established by appropriate periodic CHANNEL CHECKS, CHANNEL FUNCTIONAL' TESTS, and CHANNEL CAllBRATIONS. OPERABILITY of the individual rod position indicators is required to' determine contr.ol rod position and thereby ensure compliance with the control rod alignment and insertion limits. The OPERABLE condition for the inoividual rod position indicators is defined as being :

i l

capable of indiceting rod position within i 12 steps of the associated demand position indicator.

For power. levels bek.w 50 percent of RATED THERMAL POWER, the specifications of this -

1 section permit a maximum one hour in every 24 stabilization period-(thermal " soak time") to :

allow stabilization of known thermal. drift in the individual rod position-indicator channels during which time the indicated rod position may vary from demand position indication by ny more than t 24 steps. This "1 in 24' feature is an upper limit.on the frequency of thermal soak allowances and is available both for a continuous one hour period or one consisting of several discrete intervals. During this stabilizawn period, greater reliance is placed upon the demand position indicators to determine rod position, in addition, the 124 step / hour limit is.

not applicable when the control rod. position is known to be greater than 12 steps from the rod -

group step counter demand position indication. Above 50 percent of RATED THERMAL POWER, rod motion is not expected to induce thermal transients of sJficient magnitude to exceed the Individual rod position indicator instrument accuracy of.t 12 steps. Comparison of the demand

]

position indicators to the bank-insertion limits with verification of rod position by the-individual rod position indicators (after thermal soak following rod motion below 50 percent 'of RATED THERMAL POWER) is sufficient verification that the mntrc rods are above the insertion lim'ils.

NORTH ANNA UNIT 1 B 3/4 1-4 Amendment No. 4,N, 138 4

l

-. 1

i REACTMTYCONTROLSYSTEMS BASES (Continued)

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

The ACTION statements which permit limited variations from the basic requirements are accompanied by additional restrictions which ensure that the original design criteria are met. -

Misalignment of a rod requires measurement of pokking factors ' r a restriction in THERMAL-o POWER; either of these tcstrictions provides assurance of fuel rod Integrity during continued operation in addition those accident analyses affected by a m!saligned rod are reevaluated to confirm that the results remain valid during future operation.

Continuous monitoring of rod position with respect to insertion limits and rod deviation is provided by the rod insertion limit monitor and rod position deviation monitor..respectively.

OPERABILITY of the rod position deviation monitor is verified by a functional test at least once per 7_oays and by comparison of the Indicated positions versus the respective demand position indicators at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months . if the rod position deviation monitor or the rod insertion.

- limit monitor is inoperable, the frequency'of manual comparison of indicated ' rod (or bank),

position is increased to an interval of at least once per 4 hourc.

The maximum rod drop time restriction is consistent with the assumed rod drop time used in the accident analyses. Measurement with Tavg 2 500*F and with all reactor coolant pumps operating ensures that the measured drop times will'be representative of insertion times experienced during a reactor trip at operating conditions, t.

. a4 4

NORTH ANNA UNIT 1 B 3/4. 1 d a Amendment No. 138, l

{

H

'3/4.10 ' SPECIAL TEST EXCEPTIONS BASES 3/4.10.1 SHUTDOWN MARGINS i

'This special test exception provides'that a minimum amount ofs control rod worth is innediately'available for reactivity control when-1 tests are performed for control rod worth measurement. This special-test exception is required to permit the periodic verification of the.

actual' versus predicted core reactivity-condition occurring.as a result-of fueliburnup_or fuel cycling operations.

3/4.10.2 GROUP H'EIGHT,' INSERTION, AND' POWER DIST'RIBUTION LIMITS i

This special test exception permits individual control rods to be

{

positioned outside of their normel = group heights and insertion limits' during the performance of such PHYSICS: TESTS as those required to 1):

measure control rod worth and 2) ' determine the reactor : stability index ~

l and damping factor under xenon ~ oscillation conditions.

3/4.10.3 PHYSICS TESTS l

This special test exception permits PHYSICS TESTS to be performed -

at less than or equal to 5% of RATED THERMAL POWER and-is required to verify the fundamental nuclear characteristics of the reactor core and.

related instrumentation.

{

3/4.10.4 REACTOR COOLANT LOOPS

.This special test exception permits reactor criticality un' der no flow conditions and is required-to perform certain startup and PHYSICS 4

1 TESTS while at low THERMAL POWER ' levels.

l

-l

, NORTH ANNA - UNIT 1 B 3/410-1 Amendment No. 138, i

4

[pe ktcg'o,[

UNITED sT ATEs

.-f

( [.g NUCLEAR REGULATORY COMMISSION 5

' '/: 8

. W ASHINGTON, D. C. 20666

'g August 27,21990

....+

VIRGINIA ELECTRIC AND ' POWER COMPANY OLD DOMINION ELECTRIC COOPERATIVE DOCKET NO.. 501339' NORTH ANNA' POWER STATION, UNIT NO. 2 AMENDMENT-TO FACILITY OPERATING LICENSE.

1 Amendment No; 121

-License No NPF-7:

y 1.

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

The application for amendment by Virginia Electric and' Power Company, etal.,(thelicensee)datedApril 30, 1990, complies with !.

standards and requirements of the Atomic Energy Act of-1954, as amended.(the Act), end the Comission's' rules and regulations' set J

forth in 10 CFR Chapter I; 1

B.

The facility will operate in conformity with the application,-

y the provisions of the Act, and the rules and regulationt_ of:

i the Comission;-

i C.

- There is reasonable assurance (1) that'the activities: authorized i

by this amendment can be conducted without endangering the health--

and safety of the public, and (ii) that such activities will be a

conducted in compliance with the Comission's' regulations; f(

i D.

The issuance of th's amendment will not be inimical'tolthe common

-defense and security or to-the health and-safety of the public 1

and R

tE.

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

51 of the Comission's regulations and all, applicable requirements 1

have been satisfied.

]

d a

/f l

u

l' 2.'

Accordingly, the license is amended by changes to the Technical Speci.

L fications as indicated in the attachment to-this license amendment,'

and_ paragraph 2.C.(2)ofFac111tyJ0peratingLicense.No..NPE-7ishereby amended to read as follows:

l (2) Technical Specifications The Technical Specifications contained'in Appendices A'and B,.

as revised through Amendment No.121.. are hereby incorporated j

-in the license. The licensee shall operate the facility in 1

l.

accordance with the Technical Specific '-

1 3.

This license amendment is effective as of issuance and shall

{

be implemented within 30 days.

l FOR THE NUCLEAR;RF.GULATORY'00MMISSION-k Herbert N. oerkow, Di ecter i

Project Directorate-I'.-2 b

Division of Reactor, Projects - 1/11-Office-of. Nuclear.Rr. actor Regulation-1

Attachment:

l Changes to'the Technical l

Specifications Date of Issuance: August 27, 1990 ll t

. i ATTACHMENT TO LICENSE AMENDMENT NO.121 TO FACILITY-OPERATING LICENSE NO. NPF-7 j

DOCKET NO. 50-339

-t Replace the following pages of. the Appendix "A" Technical Specifications-with the encicsed pages as indicated. The revised pages are identified by-amendment number and contain vertical lines indicatina.the area of change.

The corresponding overleaf pages are a;50 provided tt.aaintain document I

completeness.

Page IX XIV l

3/4 1-16 i

3/4 1-17 1

4 3/4 1-19 a

3/4 1-19a j

3/4 1-20 i

- 3/4 1-22 l

- 3/4 1-23 3/4 10-5 l

B 3/4 1-4 B 3/4 1-4a B 3/4 10-1 l

e

~

s I

Z 4

ew r ev

NDEX UMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS EiClill B!E 3/4.9 RER1A ING OPEIMTIONS q

3/4.9.1 BORON 00NCENTRAT10N........................................................... 3/4, 9 1

?

i 3/4.9.2 INSTRUMENTATION................................................................. 3 /4 92 3/4.9.3 DECAY T1ME.................................................................................. 3 /4 93-3/4.9.4-CONTAINMENT BUILDING PENETRATIONS..

............ 3/4 94 3/4.9.5 COWUMCATIONS............................................................................ 3/4 ' 9 6.

3/4.9.6 MANIPULATOR CRANE OPERABILITY.................................

..............;.3/4 97

'/4.9.7 CRAN E TRAVEL - SPENT FUEL plt....................................................... 3/4 98 i

3/4.9.8 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION All Wa te r Levels...................................................................... ~............ 3/4 99 4

Low Wa ter Leve ls................................................................................. 3/4 - 9 9 a

- 3/4.9.9 CONTAINMENT PURGE AND EXHAUST IS.XATION SYSTEM................... 3/4 9 10 3/4.9.10 WATER LEVEL REACTOR VESSEL......................................................... 3/4 9 11 3/4.9.11 SPENT FUEL PIT WATER LEVEL........................................................... 3/4 9 12 3/4.9.12 FUEL BUILDING VENTILATION SYSTEM................................................ 3/4 9 13 l

3/4.10 SPECIALTEST EXCEPTIONS j

3/4.10.1 SHUTDOWN MARGIN............................................................................ 3 /4 10-1 1

3/4.10.2 GROUP HEIGHT, INSERTION, AND POWER DISTRIBUTION................... 3/4 10 2 I

3/4.10.3 P HY S I C S T E ST....................................................................................... 3 / 4 10 3/4.10.4 N>CTOR 000VWT LOOPS.................................................................... 3/4 10 4

- NORTH ANNA UNIT 2 IX Amendment No.._121, J

l 0.*

J a

.j -

i INDEX.

LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS--

PAGE SECTION 4

3/4.11 P.ADI0 ACTIVE EFTLUENTS; 3/4.'11.1' LIQUID.EFTLUENTS Copeentration...........-..................................

3/4 11-1 13/4 11-5=

Dose 4.....................................................

3/4 11-6' Liquid Radwaste Treatment.............................'....

Liquid Holdup Tanksi......................................

'3/4 11-7 3/4.11.2 GASEOUS EFFLUENTS Dose Rate.................................................

3/4 11-8

~ /4.11 13 3 -

Dose-Noble Gases..........................................

Dose-Iodine-131. Tritium, and Radionuclides in Particulate Fora...I......................

3/4'11-14 G a s e ou s Ra dwa s t e T r e a tmen t...............................

3/4 11-15 Exp l o s iv e G a s M ix t u r e.....................................

3/4 11-16.

Gas Storage Tanks........................................'._

~3/4 11-17:

).

3 /4.11.3 SOLID RADIOACTIVE WASTE........

3/4'11-18 3 / 4.1 1. 4 TOTAL ' D0 S E................................................

'3/4111-19 3/4.12 RAD 10 LOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 MONITORING PR0 GRAM...........................'...........

3/4112-1

-3/4.12.2 LAND USE CENSUS.........................................

3/4 12-13

~

3/4.12.3 INTERLABORATORY COMPARISON..............................

,3/4~12-14

.{

X Amendment No. 3 1 j

NCRTH ANNA - UNIT 2

1 1

INDE'Xi BASES SECTION PAGE 3/4.7-PLANT SYSTEMS t

3/4.7.1

. TURBINE CYCLE............................................

B 3/4 7-1 3/4.7.2 STEAM' GENERATOR PRESSURE / TEMPERATURE LIMITATION...:.......

B 3/4 7-4 t

3/4.7.3 COMPONENT COOLING WATER SUBSYSTEM;.......................

B 3/4 7-4 3

3/4.7.4 SERVICE WATER SYSTEM.....................................

B 3/4 7 3/4.7.5 ULTIMATE HEAT SINK.......................................

B 3/4:7-5 3/4.7.6 FLOOD PROTECTION.........................................-

B 3/4 7-5 3/4.7.7 CONTROL ROOM EMERGENCY HABITABILITY......................

B 3/4.7-5 3/4.7.8 SAFEGUARDS AREA VENTILATION SYSTEM........................

B 3/4 7-5 4

3/4.7.9 RESIOUAL HEAT REMOVAL SYSTEMS..

B-3/4 7-6 3/4.7.10 SNUBBERS....................

B 3/4.7-6 3/4.7.11 SEALED SOURCE CONTAMINATION..............................

B'3/4 7-7

(

3/4.7.12 SETTLEMENT OF CLASS 1 STRUCTURES.........................

B 3/4'7-7' 3/4.7.13 GROUNDWATER LP.'EL - SERVICE WATER RESERVOIR..............

B 3/4 7-9 3/4.7.14 FIRE SUPPRESSION SYSTEMS.................................

B 3/4 7-9 3/4.7.15 PENETRATION FIRE BARRIERS................................

B 3/4 7-10 3

3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1 and 3/4.8.2 A.C. AND D.C. POWER SOURCES AND-l DISTRIBUTION................................

B 3/4 8-1:

1 NORTH ANNA - UNIT 2 XIII

i 1

AIDEX BASES

~~.

~.

.n

.~.

i M

M 3/4.9 RERVI IhlG OPERATIONS 3/4.9.1 BORON 00NCENTRAT10N............................................................B 3/4,91 3/4.9.2 INSTRUMENTATION....................................................................B.

3/4-91.

3/4.9.3 DECAY TIME..............................................................................B :

3/4.91 1

1 3/4.9.4 CONTAINMENT BUILDING PENETRATIONS.................. B

.3/4-91 3/4.9.5 ColWUMCAT10NS........................................................................B 3 /4 91 i-3/4.9.6

MANIPULATOR CRANE OPERABILITY......................................B 3/4 9 2.

3/4.9.7 CRANE TRAVEL SPENT FU EL PIT...............................................B

.3/4 9 2' 3/4.9.8 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATON..............B 3/4 92 3/4.9.9 CONTAINMENT PURGE AND EXHAUST ISOLATION SYSTEM...........B 3/4 9 2.

3/4.9.10 and 3/4.9.11-WATERLEVEL REACTORVESSEL AND SPENT FUEL PIT.................................................B 3/4 9 3 3/4.9.12 FUEL BUILDING VENTil.ATION SYSTEM.......................................B 3/4 93 4

3/4.10 SPECIALTEST EXCEPTIONS i

3/4.10.1 SHUTDOWN MARGIN.....................................................................B 3/4 10 1 1

3/4.10.2 GROUP HEIGHT.lNSERTON. AND POWER DI STRIB UTION UM ITS.................................................................B

'3/4.10 1 3/4.10.3 P HYSI C S T E ST S.............................................................................B 3/4 10 1 3/4.10.4 RFJCTOR COOLANT LOOPS............................................................B 3/4 10 1-i i

NORTH ANNA UNIT 2 XIV Amendment No. 121,

/

1 l

.. J

1 REACTIVIT! CONTROL SYSTEMS.

~S_URVEILLANCE REQUIREMENTS 4.1.2.8I Each borated water source shall be demonstrated OPERABLE:

a.

-At least once per.7 days by:

.1.

Verifying the boroniconcentration in each water. source,

~

q 2..

Verifying the contained:barate'd water volume of each water-source, and

3..

Verifying the boric acid storage. system' solution' temperature d

b.

At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 'by-verifying-the RWST temperature, i

l

'l i

NORTH ANNA - UNIT 2 3/4 1-15

.l

)

REACTMTYCONTROLSYSTEMS y

3/4.1.3 MOVABLE CONTROL ASSEMBUES GROUP HEIGHT UMITING CONDmON FOR OPERATION 9

p 3.1.3.1 All shut $own and control rods shall be OPERABLE and pWoned within 12 steps *'

of their group cp counter demand position.-

APPLICABILITY: MODES 1" and 2".

ACIION-a.

W!!h one or more rods inoperable due to.being immovable as a result of excessive.-

I l

I friction or mechanical Interference or known to be,untrippable, determine'within =

l one hour that the SHUTDOWN MARGIN requirement of Specification 3.1.1.1-is

satisf.ed and be in HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

i b.

With more than one rod inoperable dud to causes other.than those addressed by ACTION "a" above or misaligned from the group step counter demand position by more than the above alignment requirements, determine within one~ hour that the SHUTDOWN MARGIN requirement of Specification 3.1.1.1 is satisfied and be.in HOT t'

STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

c.

With a maximum of one rod inoperable due to causes other than those addressed by ACTION *a" above or misaligned from the group step counter demand position by

(

more than the above alignment requirements, POWER OPERATION rnay continue

/

provided that within one hour, either:

1.

The rod is restored to OPERABLE status within' the above alignment requirements, or 2.

-The rod is declared inoperable and the SHUTDOWN MARGIN requirement of Specification 3.1.1.1 is satisfied. POWER OPERATION may' then continue provided that:

a)

A reevaluation of each accident analysis of Table 3.11 is. performed i

within 5 days, ' This reevaluation shall confirm that the previous analyzed results of these accidents remain valid for the duration of j

operation under these conditions, and '

j i

For power levels below 50% of RATED THERMAL POWER, the position of each rod as determined by its individual rod position indicator may be more than i 12 steps from its

?

group step counter demand position for a maximum one hour in every 24. During this l

hour, the indicated position of each rod may be no more than i 24 steps from its demand i

position. The 24 step / hour limit is not applicable when control rod position is known to be greater than 12 steps from the rod group step counter demand position indication.

See Special Test Exceptions 3.10.2 and 3.10.3 NORTH ANNA UNIT 2 3/4 1 16 Amendment No.121, l

t

^

i REACTIVITY CONTROL SYSTEMS LIMITING CONDITION FOR OPERATION'(Continued) b)

The SHUT 00WN MARGIN requirement of Specification 3.1'.1.1

+,

is determined at least.once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , and c)'

A power distr'ibution mapuis obtained'from the movable incore detectors and F (Z)-and.F g are verified to be-q within>their limits witiin 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , or l

d)

Either:

4 1)

The THERMAL POWER. level is reduced to less than or-i equal to 75% offRATED, THERMAL POWER withinione hour and within the'next 4: hours the high' neutron flux:

(!

trip setpointLis. reduced to is Lless.than or equal to 85% of RATED THERMAL POWER, or 2)

The' remainder of the rods in'the group with the i

inoperable rod are aligned to within-t 12: steps of-the~ inoperable rod within the hour while maintaining the thermal. power, rod sequence, and insertion limits of Specification 3.l_.3.6 during subsequent l operation.

I l'

SURVEILLANCE REQUIREMENTS i

l-

.i l

4.1.3.1.1 The position of'each rod shall be determined to be within the group demand. limit by verifying the individual rod positions at least once per-12 hours except during time intervals when'the Rod Position Deviation Monitor is-L inoperable, then verify the group posif. ions at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

\\

4.1.3.1.2 Each rod not fully inserted shall be determined to be OPERABLE by movement of at least 10 steps in any one direction at least once per 31 days.

NORTH ANNA - UNIT 2 3/4 1-17 Amendment No. 121, l

4 y.

.<-r+

- = - - -

-- - - - - - - - - - - - - - - - - - - - - - - ^ - - - - - - - - -

t l-

,f i

I JBLE3.1-1 ACCIDENT ANALYSES REQUIRING REEVALUATION i

IN THE EVENT OF AN INOPERABLE ROD s

p j

Rod Cluster Control Assembly Insertion-

- i Characteristics-Rod (50 ster Control Assembly Misalignment-7 1

Loss of Reactor Coolant from Small Ruptured i

Pipes Or From Cracks In Large Pipes-Which Actuates Tht' Emergency Core Cooling System.

.i Single Rod Cluiter: Control. Assembly Withdrawal.

At Full Power Major Reactor Coolant System Pipe Rupture (Loss of! Coolant Accident)

. Major Secondary Pipe Rupture

- t Rupture of a Control Rod-Drive Mechanism Housing.

(Rod' Cluster Control Assembly Ejection) t 4

-l 4

l 1

l NORTH ANNA - UNIT 2 3/4 1-18

~.

^

3 a

I REACTMTY CONTROL SYSTEMS -

POSITION INDICATOR CHANNELS. OPERATING UM! TING CONDITION FOR OPERATION

+

3.1.3.2 The shutdown and control rod position indicating system shall be OPERABLE with:

j a.

Each individual rod position indicator channel,1 per rod, accurate to within 12 steps

of actual rod position,' and b.

Each demand position indicator, ~1 per group,' accurate to within ! 2 steps of demand position, and c.

The Automatic Rod Position Deviation Monitor with the' alarm setpoint < 12 steps.

/

APPLICABILITY: MODES 1 and 2 AGIlQN.

a.

With a maximum of one individual rod-position indicator channel per group inoperable, either:

1.

Determine the position of the non indicating rod indirectly by the movable ' 'l incore detectors at le ast once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months and immediately after any motion of

' the non. indicating rod which exceeds 24 steps in one. direction since the last determination of tha rod's position as wsfl as verify that the rod position f requirements of Sr ecification 3.1.3.1 are satisfied, or e

2.

Reduce THERMAL POWER to < 50% of RATkD THERMAL POWER within 8 i

hours and ver;ry that the requirements of Specification 3.1.3.1 are satisfied.

b.

With a maximum of one demand position indicator per bank inoperable either:

1.

Verify that all individual rod position indicators for the affected bank are l

OPERABLE and that the most withdrawn rod and the least withdrawn rod of the bank are within a maximum of 12 steps of each other at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months , or L

2.

Reduce THERMAL POWER to < 50% of RATEDTHERMAL POWER within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months and verify that the requirements of Specification 3.1.3.1 are satisfied.~

l c.

With the Automatic Rod Position Deviation Monitor inoperable, compare the-demand position indicators and the individual rod position indicator channets. at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months to ensure that rod position indication is within the above tolerance requirements. The provisions of Specification 3.0.4 are not applicable.

~

Below 50% power each individual rod position indicator may be more than i 12 steps from t

its group step counter demand position for a maximum of one hour in every 24. During this-hour, each individual rod position indicator may be no more than 24 steps from its demand position, if either the one hour period or the 1-24 step limit is exceeded, immediately declare the individual rod position indicator channel inoperable.

NORTH ANNA - UNIT 2 3/4 1<19 Amendment No.121,

.,.,, ~.,

, +., _, -

8 3..wm gC{ y..e-my-Sf. gi N g M[ j +;.:_ W,m,.[. g,: %, -

-n

- w

[- @- s.y @* y..3

. =

a%> @$ q w

1. =- m..

n.

x

.. w,,v Qg%w~F - :

qay:w m i n#,,, MK.,M,."

&m o a

y

. - yk-p %. yw $+ y)h j=--

e r#om@w%_mgx

/

mg4g.

g g

ewowa-s m

w-u u.

wm a:w a

.m

- wg%.%;+^ a&.r+" m. y> 3, 4m.w~/x 3,.

gyy. aum ns wm a.a,y ~-

Ar s y a m..

gk b* w, c.

w u

s y, - f..1; Q :,i 4 w* L:3.4 f:8 T

w1^

s k

. -?

L1~vt.1. 5 -

h -- <

uw v.

x

= n.=iJ_ +O. n - - '

1 s"

~ m

.yn w

u.

? $'.:>a w M -9 He- ;

m il',

. U. ' -?

fl.j z<s.:

a

.v-

\\1 k-eW.'

t O,.&( t r.s :

L'."O ki ; g- + !

tr t

~q sm k

47

, -. '.. VO ; d W M V.

1;- (b, JE

. +

h -

, $t-3;W.J W3' 4

% 3 y _rQ 4 ' : g f7_q'. A.N f 9 *.. -

-P.. +

1;>

g'.[-~

-.9

$\\

',J.

[r('+1 O, g % e' y 1

y. :_,. ' x i

4 yH.l' r

-e 4

4 g..a' 3 1.~ -i hv m3 e-b ig7 -+ %

,pk.

'w 4'-4' m'. '.i-4 M-5.

e,

't e' _ - -

A W' N-2?q, '.

-,1':

/,,e 1 a,,-

y.r.f'. y N.V'[

F

'b--'

s^,

'+d

.'a

..,-hh;r'.'

.,.tx s - : : w

_4 g

a" g.-%'.'

fO

- j - _+

4 i. _,N,

g.

y 1 h_ 7 c?M M M A.

N _

V.

a

'g

,'L'._b i

,a T

~ 1 h',,- = g

[N-l ;

p.

,, s.3:

g p

h-7

- M :&.5 fj','

E;'h ?

,i

'-m'.

s w[E 4.:!'-f l 4; L y: 3,A n'I

/ -

m..

-v c-v' 4

t

~ ogt h-. _e--

g

- m.y m,.-

t q

t

,r_ +_c -

2.m_

1

=.m.

1 l

-f3-3[+: OIT,2 4. e !"

21 %

O, +MM1,7 y 9 ' I.,9 -

.[. w..', k:

4. (Me, p',g y"

.i n

yW

-A b.

5.,

g ",

~y y t_.a -

r w' :,

p y {.. '. 4 t.,

.v n

a+ l.,

4f 53 g 2c c

<< m r.

s

-..,~,r

f17 it i

3 U_

3 R,,.7 S.-

u-g i; 3-f+.f,,p,

> ~ 3 p:.4g gM sg % % c[n,r p 2w,

< ' 11_ gl y n}.t 4y.v 4 -- y n'm g-_a 4.d A_a ; 8 -

. I

'-. 41 7

1

[_

i d:

- Q.y ; p

_ _ y M-' p r -

5 c) Q

_, x r

a

<-e te q+-t 4,.g j? m -

t e

9-v,.2

.i.

e. M.

,A o

y c p-u

-+ o _. cyJ

,.-g;W

+ a A3 n. a-g, 2 -m,g jf - -

W--t :sj p_ e 1-

. e i+

.mm 1

-4

.-; v mw a p,n.

c

<1 4 y

2 a-s e. -.

np

~

m

= t,2m. Ac J

..e

<N:v--..

.. 4 -

4

' ' -. t 1

r

a

a.,-_i.- r. jm s-nm e.

q

-f.y K'p'[n-e,4u

,j

' g o,4 ms

= m' n.

=

m - w.;,.

4 m,1 g_s.,5% {f x.-

u. -*

e 3

a c,-

y: [

c

. 4 44,

4-n n.

' n.)g i j'

p,' 'j gg 1.

--.!p, g

' k '. j y

. Q-r. m

-y- - +,

, y

.. - e

(

3 2,j oi [ r.

r f

5. y.i ?

Y

.3, 4

gQ.-3 wg '

g'%,3 fp.y &&;mg.

e-, y 7. :5.-c

( gm>

s_ v p.-

t

n e p ;t

/,p-

m,, f _;

M W _

s,, -

.,s' 9 L " %.u f

.a-y

- M;q,m,.

_ c

+

u' c ;< " G J-_ M3

,2;4_

.c;4-M t-p 9 JJs m

m m.

m, ~ -Agg.W (..*,.V f_ M.

> v

ve

.i--

yy.g p g3 f. sy- = ; = f. fiQ-,f '< ;w;.8 r 2

4

.g%mMy,

~~m

-3 t

-!,A

~'.t-

- e Ammw y_

a,.,4:'

((

~

_.1

/, - %.vn. M

u s

+

m, +

3 -

1.

1 14/ %

. N. m...W.

+

n k, " A, QM

3. [#

9

'4 5

.. y f f

-- m'1. i g ;,

"yI' w

+ 1

--->,a v

r p.g

~.a.

ky y.[: -,.'.

gy

',-;h4 8'

/

-j+'-

y

'-[i

.r

?

-T-

~

'[

-,j{- 1

.g j

k,

, a n* '

-e'*

j 9 M. -

yy 3:

Q,_--N T'

t

,1_

I F

?- M

,i C

y' p

3 -:

{--- -

y, f '4'

'i_k,y fr

.;,,/#,

r f - i ~.

a.-

-. ' 1 v.g 3

?

-m

.=.

c.

c

. v 2 <

si 4

'"-, I g # ; 41 C.[-

!t I

Y

.z,f,4 ;j,

. G. W,.' "

I JI D 0;3 4.

c-u-

- 9=

g y

',=g-3=

_a.

y, N f

,_4, s'

j q_.. _.

(

7

-.n

.L. _,

v y 39: n s

9i y'

?

_5=

e l '..

g 's - :

m_ n cs__,4V'i c-s %. _:

+

i u.

5k

".r

,,c

,,a

,4.-

a*

H 4 "w e

(--go iW'-

t tt a

v w

r i"

q n. t ' - : a-

% 4 e a.,= E.u " - sl)g

-;p

,Y,*

--e

-1iO 5 j.,,.

+-

3 4

_.. c. s.gf._i g i.),2 ] y 1

.. +

3 1

{=.,,?,,

_E

>-9 1

j

%r' '1 p-.. y

> g > + > -}y;-

a t

.-.!+ '

,-t

=,

g... g j u

r

-a

'1

,. y_ S.

)

!b

'l C M ', '

l 5

-^ s g r:s 3

g q,j.

,4 s

4

/

EJ.1

( b3. ~- ') #

k

-Ya

= -. -". i

' 3{ d

-'M

'*I

t--

j i r,;_-,

g 3

$ u" : c :4

.D^

e

.<.,i'i))t t

'N '.

. ki i g

T 4

V.,~33; ed,'+

,','N 4 %@~ :J

_ s pV s

)V 4 4

r' j } ( 3 -. +D,.,..- -

)

g s

r 4g r,

, %[# h i

(;2 ! j k

- Y[e

-- _ y :- ~

M'l e k.,1i t.$

E{g i

.7 i l 1-p T

=

u

)--

m

-2 w m.,

=p W' Y.

1_5

- Ny.'

-..n v,

16 s t

y

'4....

MT :-' - - - -

)

4. j ; j;; p'4 a,n ;,- _. };

r

-4 d a.'

2 M^ u.N-t '-

% ~-7 Ik4 e.

ha e, 4

S

,m, P,

i.'n 4

(

,- 5, S p; s.

t g = r] q g;

I,4 ts.. - +

'1%-

%g -

.p 4,

c'y 2

1 i.

Mi t r

s.;I,_

pty;

-*q

, s4 l s, 4

1 ?

~

M Tn - i +

=. i l sy 1

s 3

ve' 1

+

,y, i

+ 14 e

q q 'a N..

f tnb ' g >

.Q, m 2 i

i..;

hn @

i t

-I.9 m

s.t*

i c'; ' hig

- pv p g,

(;q -

wn 3,

11 d +3

' k.9 o it

'g!n p w}Q Q.. M

-ir 7;

s u,

m 7 [_ s _.- ;(s

'f,y

-l f:f< '

..q '

4

((g nya

?

+

' i s

_p r y 4

s 1

1 (y.

.a ;f l2 )5,;grm g y

L

_ - a

+

m.

t1< "

' J l.

7 1

if4IP fM f',

4 i

y.

.;e

.z 1

+

-.8 [ y,..g.y 1

y n

s t.

,e g ;; '

y 9

hb I

.a p

7

+%

9 yy.^

f j

y3._

4 er t' 7 4 -._

8 b ':-.

E.

p.

5

\\

T

}

,,_q

.J.

45 t

3 6

b k,

i Ik

.e5 i

i

)

v/m

,.wam O.g

,y.c p+

dt n

w._%c

=.. -w

_x_"

.? ;@! ) -

<-j.

O. g _, - 6p' _ h 1

5

,g..%, =

-1

,:/'~

j *m'_.j' '(

U.

m>

^%

s'. ',.3+_ y' i 3;{._*

f'%*'

W

T f'

?

' l_ ?.-

L

,4l',

t

'_q,e.

':_y J k-y_

i.i ' g "e

4"+2-

.i p...,..n.

3 h 5 r

;p-y.

T1

. - s,3 p~ g' j

.,e t

L

,f, s

-2 z_

4

..n

-, p

,e.R.r

,.q:-

9

- ~ -. >

c u

+

9 14

?

4 th

- {- n y

j A

l z-

)

2m

-m,,.-*

t

?

y.- t' !6,::b' Vi

_i

~

g e

s

.h*

f

~

1V

, ?

.s a. ? J.,

1

\\ ' r 's s '\\' e

7

'-'h 5

i nb -

2 w :-

1 e

n-

?

t oaks

,X ([

Q.y ;

[G y 3 >3 f w.,

t-w

y t

r, r:

a

=..m.-

1'

-me

~.

i ( -

g Q,

.Ij-N,[

g I

'p

..U.-.M l }

3'

=

, )[ -.. p '

I I

',"'4 i -

g_

y(

m.,3 e

3 g.

(

4 i

p%r j

i -

k y

4 y

1

> '=

r

=

4

=,- -

+

s c

4_

, 4,'.y'. 7, ' ' '

g L

4

< +j..

,5 O

. m h"

-.'A v' t

I s

"b f6 f ai n

<,4 J,)_

.ri,..

;L "M-

W '\\ "i

.4i-F:

+

ns'

-<?-

x-

~

n r

a w _.

-t-t y yo-4 f.+.

}%. mL Q-3 3

.c_'

5 h,-

e 7]

< p Wl -'

t 2

Q i f ', y9 s.

)

{_

a.r l t

om y

_g n,x...

t %w z

3 t - i u

d

. - -- \\ 6~ '9-.-_

etR j

wtC

's 4

i

=

1.

1,=

o...._

i^. e '.,.:'i a.1 s

v s

y

i PR '.

c-

-(3U

'4.1

' x '3'

(

')- r i

yn

,A_:- (

4 4

w_

'Y; 9p 3

' " (Q-(4; hij d

'T d{

3 i

s t

i 4

is,.::

.;r

>i.

[ -'[

_y r, g[- hr.,-

4 p'

g 4'

. J ':'.g.

[ g '.4

[V 'N i-- j

- ).-.

jy'[> yA c 4

E

(

\\

i.

3:g.

y g

'., r,

+

,k 1

s

, lld'

(%!

v(

+

w, g-4 s'

hu*

Y

- Q:

A 1 1-1 y

4

'i s u C).x 1

.y 3

3 g

1 hr

/

4

+

i

?y3 1at' i AP

(

j 14.

s' y

h N

it'

%'^

J'{

p' v;,' g

- n m

f f..

g j q ' t.l f _,

SQ'7 _

g

7. Aj 4

w:.

a;-. m, :, *n p

g

, +'

r

.y! i[NM,

N f',?

~

nS N 4-4 3r' t

3 gge.:

Q> t a

[v

= 1 n,.

+

a

-.4. s '. y c ~

e -

1 g'

j"*.

,c g

m e

~

,4!

=3.'.

., -+ q' N

,t

_i-.n 7,. f}.:

et jp. ! r:.

j 3

1

-p.,.

E: t 43 m, > >. -.e i sWI 4

m i.

p. @.g_ ;d'y ['s]p; i M

,w,

=.

k k

6 b,

f e c.,.'

4 4

'i v,

,t

]

(

h 2

.6I l' y'.%,7 -

j'y g

mm-

,? T:n

.3 q '. w g_ f f ;

+

. { $,

r

<:--.t.

YN,

[wn-h

}

@t>

.., tg i

L s

) ;,' '

r.

1.:, s v i*

. lA c

C du

... >: ! X a-_

w

+

s

.,N t (3,4>

g-gf._. =

p i

n 1.-

, h & !-

g s

sst

,.s E

.3.=

_s.

i s s -

-. t y'.

ap q - %

3

{

'p'; S ;v g

a r

n

~

w g'

N T

,E-

-~'b'J.,_',

g.~

i 1

f

.s, t --

A' _{ g.

.T eR i

j

, qq:f,v, s e.

c pt y

,. i r

q

..>q

4 - +

C

.:'i

.g -

j,e c

q g<;r 4

m i.

.4 1

- s t

J.

I 3

\\'.

1 1

P-

[

q'

.,- k';I f ) ^

9 -

y y

iiD ' t 4 ;;.

m.

g ~e i / -;

f.

I:v. 'T 2

u <.

s k,i Tf / M, k T'l

, )'.

J

8 s

g 4

1

- t et_1, y

q);eq\\

.1,-

,:9. :x ui

.v

.m..

2 >>>

-q

.u 9

.trv

-. y.

,s g..

i 2

,,r os (e

t-D

>~.-Q.y;

,, g >

a 1

4 4.7

.j

(

n ?' '

X (Q *-

_'h'--

t

?

h b'f <*.f f-

._. l e.f b

?

f y

g.1 d 'i r,M 4

t Nl @ "

i :$:...1 T,J E. / --W

+'.I ys a

um

, 3,. 9 { f'

' s if r '

,7 i

,g 4. ',

iA..'

i)O ' "7

' n..

4 Mg; d'i d -k]

mw n

-.f

,.t r-Ii j5

^

p y

, ^., t ;

-2.,. -

JL.:;sf.

P 4 -

. s.<-

z

}

?-.<

g{-

g

, g ps'

( p%

_1 1

p.4 i

M'd u, a h

N

- -* 's '; I

'~.

p

^.b-i1 j'

+

I h 1

-IY hs

L g'

t Qi1 ff 2

75

.dii ^

iX j f..

3

i

y

' (d !.

,y

-f

[

{

3 5

w y

p,

i w

-. s? ' d W.3;'Yf

.i

,l v,.@.. -

4 Mi-4

.a=

t, y

Iid 't (y 4 f 4

1

. ~h -,t r

.c r,

= a (s

-} (q -

.y--

.cg

,-[(ii_

n u a . -A'1

-f [f J.;2r

-g g ] 7 < g.

4 p

4

% 4 g

t ut t h ~': $k. p.

,. lY.

4, hQ

& *f l ' f, m ;p p),,'

s y yv-y 4' Q;t '

)v k

l T%

w

~

pp 8

4 j

REACTIVTlY CONTROL SYSTEMS POSITION INDICATOR CHANNELS OPERATING SURVEILLANCE REQUIREMENTS j

4.1.3.2.1 Each Individual rod position indicator shall be determined to be OPERABLE by:

a.

Performing a CHANNEL CHECK

by intercomparison of each individual rod position

+

indicator and its corresponding demand position indicator at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , and b.

Performing a CHANNEL FUNCTIONAL TEST and CHANNEL CAUBRATION at least once per 18 months.

1

~ 4.1.3.2.2 Each demand position indicator shall be determined to be OPERABLE by:

a.

Performing a CHANNEL CHECK of tne demand position indicators within a bank at i

least once per 7 days, and b.

Performing a CHANNEL CHECK by an intercomparison of the control bank I

benchboard demand position Indicators and the rod control system logic cabinet bank overlap indicator or the rod position indicator cabinet P/A indicators, and determining their agreement within 2 steps, at least once per 92 days.

4.1.3.2.3 The Automatic Rod Position Deviation Monitor shall be aetermined to be OPERABLE by performing a functional test of the process computer alarm to demonstrate _ the process computer remains capable of recognizing a deviation of 12 steps or more at least once per 7 days.

q Below 50% power each individual rod position indicator may be more than 12 steps from its group step counter demand position for a maximum of one hour in every 24. During this hour, each indivklual rod position indicator may be no more than 24 steps from its demand position. If either the one hour period or the 124 step limit is exceeded, immediately declare the individual rod position indicator. channel inoperable.

A-scan frequency of approximately once per minute, by either the plant computer or a data acquisition system, is acceptable for determining the total time that a rod position indicator has deviated more than ! 12 steps but no more than t 24. A rod position indicator which is found to be so deviated is assumed to have been deviated for the entire scanning period.- When the scanner is unavailable to sum deviated time, the toldiance reverts to i 12 steps.

NORTH ANNA - UNIT 2 3/4 -1 19a Amendment :No. 121, i

,f,n --- -

.e.n..

~.. _ _ _ _

REACTMTY CONTROLSYSTEMS POSITIONINDICATORCHANNELS SHUTDOWN UMITING CONDITION FOR OPERATION 1

t 3.1.3.3 The rod group step counter demand position indicator shall be OPERABLE and accurate to within ! 2 steps of the demand poution from the logic cabinet for each shutdown or control rod group not fully inserted.

AEEU ' ABILITY: MODES 3*,4* and 5*.

ACIlW:

With less than the above required demand position indicators OPERABLE, open the reactor trip l

system breakers within 15 minutes.

4 i

SURVE!U.ANCE REQUIREMENTS 4.1.3.3 Each of the above required demand position indicators shall be determined to be OPERABLE by:

a.

Performin; a CHANNEL CHECK of the demand position indicators within a bank at least once per 7 days, and b.

Performine a CHANNEL CHECK by an. intercomparison of the-control bank benchboard demand position indicators and the rod control system logic cabinet bank overlap indicator or the rod position indicator cabinet P/A indicators, and determining their agreement within 2 steps, at least once per 92 days, c.

The provisions of Specification 4.0.4 are not applicable.

.l u

With the reactor trip system breakers in the closed position.

l NORTH ANNA-UNIT 2 3/4 1 20 Amendment No. 121,

REACTIVITY = CONTROL SYSTEMS' l

R00 DROP TIME LIMITING CONDITION FOR-OPERATION 3.1 3.4 The individua'l full length (shutdown and control) rod drop time from

~

the fully ~ withdrawn position shall be less than or equal.to 2;2 seconds from beginning of decayL of stationary-gripper coil voltage to dashpot entry with:

j T,yg greater than or equal to 500*F, and a.

b.

All reactor. coolant pumps operating.-

[

~

m APPLICABILITY:

MODES 1 and 2.

4 ACTION:

i i

a.

With the drop time of any f'J11. length rod determined to exceed 1

the above limit, restore the rod drop time to within the above-limit prior to proceeding to MODE 1 or 2.

b.

With the rod drop times within limits but' determined with 2.: reactor l

coolant pumps operating, operation may-proceed provided THERMAL

l POWER is re:;tricted to:

1.

Less than or equal to 66% of RATED. THERMAL ~ POWER when the reactor coolant stop valves _.in the nonoperating loop;,are open. or

-j 2.

Less than or equal to 71% of. RATED ~ THERMAL POWER when the reactor coolant stop valves in the nonoperating loop are closed.

4 SURVEILLANCE REQUIREMENTS i

4.1.3.4 The rod drop time of full length' rods shall.be. demonstrated through measurement prior to reactor criticality:

For all rods following each removal of the reactor vessel-head, a.

b.

For specifically affected individual rods following any main-tenance on or modification to the control rod drive system which could affect the drop time of those specific rods,'and c.

At least once per 18 months.

NORTH ANNA - UNIT 2 3/4 1-21

.w.

QCONTROLSYSTEMS SNtnDOWN RODINSERTION UMtT UMITING COND(TION FOR OPERATION' 3.1.3.5-All shutdown rods shall be fully withdrawn.

APPLICABILITY: MODES 1* and 2'#.

ACIK11:

With a maximum of one shutdown rod not fully withdrawn, except for surveillance testing pursuant to Specification 4.1.3.1.2, within one hour _ either:

a Fully withdraw the rod, or b.

Declare the rod to be Inoperable and apply Specification 3.1.3.1.

i SLAVEILLANCE REQUIREMENTS I

-a 4.1.3.E Each shutdown rod shall be determined to be fully withdrawn:

a.

Within 15 minutes pr!or to initial' control rod: bank withdrawal.during an l

. approach to reactor criticality,.and b.

At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter.

See Special Test Exceptions 3.10.2 and 3.10.3.

With Keff 21.0 NORTH ANNA UNIT 2 3/4 1 22 Amendment No. 121, l

j

4 ~

?

REACTMTYCONTROLSYSTEMS CONTROL RODINSERTION LIMITS LIMITING CONDITION FOR OPERATION l

3.1.3.6 The control banks 'shall be limited in physical insertion as shown in Figures 3.11 and 3.12.

APPLICABILITY: MODES 1* and 2'#.

ACIQl:

I

.t With-the control banks inserted beyond the above insertion limits, except for surveillance testing pursuant to Specification 4.1.3.1.2, either:

a.

Restore the control banks to within the insertion limits within two hours, or -

]

b.

- Reduce THERMAL POWER within two hot'rs to less then or equal to that fraction of RATED THERMAL POWER which it, allowed by the rod group step position counter.

l demand using the above figures, or I

c.

Be in HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

(

SURVEILLANCE REQUIREMENTS 3

4.1.3.6 ' The position of each control bank shall be determined to be within the Insertion.

limits at least once per'12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months except during time intervals when the Rod insertion Limit Monitor is inoperable, then verify either the individual rod positions (indicated positions) or the group step counter demand position of each rod group to be within the insertion limits at--

least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

i 6

b See Special Test Exceptions 3.10.2 and 3.10.3.

With Keff 21.0 i

NORTH ANNA-UNIT 2 3/4 123 Amendment No. 121, l

3 1

1

-l L

FULLY WITHDR AWN 1

d 228

(.54, 228)

^

l 220

.. a..

a I

200 j

(1,1M)~

! BANK Ci l

l-

.j 3

g"-

180

'lL

~I t

'I

$ 160 t

I l~

..1 l

l-t

140 i

(' :

1 a

v

[

i g

j.

i

,4

$f 120

,(0,118)

[:

i 1.

m

. I I

l...

e' too i

[i SANK D i

g

__2.._

.2 g

O I

.O 80 a

g i.

4 i

60 -.

i.- f.-

m i

j.

.- s

. -y

.,)

n so i:

l_ fi i.

f, a:-

i 20

= [! --

l-

...;.. s.. _2....l.2..

j F

- j y (.048,0) -i

. i --

0

.1

.2

.3

.4

'.5

.6

.7-

.8 c.9 -

1.0 ~

FULLYINSERTED FRACTION OF RATED THERMAL POWER Figure 3.11 Rod Group insertion Limits Versus Thermal' Power

' NORTH JNA~- UNIT 2 3/4 1-24 1

j

_ t.]

'~

8 V

)

I i

t

-s'

.I P

a o

i 4

'I

(

I THIS PAGE DELETED l

'i i

I

)

I p

'i

\\

NORTH ANNA. UNIT 2 3/4 10 5 Amendment No.. 121, 9

4

.m m

s

)

i i

REACTIVITY CONTROL SYSTEMS BASES 3/4.1.2 B'ORAT10N SYSTEMS The boron inject (on system ensures that negative reactivity control is available. during each mde of facility. operation.' The components required to perfom this_ functb 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 diesel i

generators.

~

7 With the RCS average temperature above 200'F, a minimum of two boron.

injection flow paths are required to ensure single functional capability in the event an assumed failure renders one of the flow paths inoperable. The boration capability of either flow path is sufficient to provide.a SHUTDOWN' MARGIN from expected operation conditions of 1.77% delta k/k'after xenon decay.

l*

and cooldown to 200'F. The maximum expected boration capability requirement occurs at EOL'from full power equilibrium xenon ~ conditions and: requires <

v.

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 l

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.

o The limitation for a maximum of one centrifugal. charging pump;to be OPERABLE and-the. Surveillance Requirement to verify all" charging pumps except-the required OPERABLE' pump to be inoperable below 340'F-provides assurance'-

that a mass addition pressure transient' can be relieved by the operation of a single PORV.

l The boron capability required below 200*F,is. sufficient to provide a SHUTDOWN MARGIN of 1.77 delta k/k after xenon 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 l-water from the refueling water storage-tank.

i-NORTH ANNA - UNIT 2 B 3/4 1-3 Amendment ~ No. S'4', 78 APR 1419tp

.. ~. - -..

g REACTMTY CONmOLSYSTEMS BASES

-l 3!4.1.2 BORATION SYSTEMS (Continued)

The contained water volume limits include allowance for water not available because of

~

dis;harge line location and.other physical characteristics. The OPERABILITY of one boront injection system during REFUELING insures that this system is available for reactivity control.

while in MODE 6.

]

l L

The limits on contained water volume and boron concentration of the RWST also ensure a l

l pH value 'of between 8.5 and 11.0 for the solution recirculated within the containment after-a' 1

LOCA. This pH miniml::es the evolution of iodine and minimizes the effect of chloride and caustic stress corrosion on mechanical systems and components.

At least one charging pump must remain operable at all times when the opposite unit is in

)

MODE 1, 2, 3,.or 4.

This is required to maintain-the charging pump cross. connect system operational.

g 3/4.1.3 MOVABLE CONTROL ASSEMBLIES The specifications of this section (1) ensure that acceptable power distribution limits are maintained, (2) ensure that the minimum SHUTDOWN MARGIN is maintained,' and.(3) limit the-potential effects of rod misalignment on associated accident analyses. OPERABILITY of the.

=

movable control assemblies is established by observing rod motion and determining that rods-are positioned within 112 steps (indicated position) of the respective demand; step counter position. The OPERABILITY of the individual rod position indication system is established by appropriate periodic CHANNEL CHECKS, CHANNEL 1 FUNCTIONAL TESTS, and' CHANNEL CAllBRATIONS. OPERABILITY of the _ individual rod position Indicators is required to determine control rod position and thereby ensure compliance with the control rF1 alignment and insertion 6

limits. The OPERABLE condition for the individual rod position indicators is defined as being capable of Indicating rod position within i 12 steps of the associated demand position indicator.

For power levels below 50 percent of RATED THERMAL' POWER, the specifications of this i

[.

section permit a maximum one hour stabilization in every 24 period (thermal " soak time") to-L allow stabilization of known thermal drift in the individual rod position indicator channels

~

-I during which time the indicated rod. position may vary from demand position indication by nol more than i 24 steps. This *1 in 24' feature is an upper limit on the frequency of thermal soak allowances and is available both for a continuous one hour period or one consisting of several discrete intervals. During this stabilization period, greater reliance is placed upon the:

demand position indicators to determine rod position. In; addition, the 124 step / hour limit is not applicable when the control rod position is known to be greater than 12 steps from the rod group step counter demand position indication. Above 50 percent of RATED THERMAL POWER, a

rod motion is not expected to induce thermal transients of sufficient magnitude to exceed the Individual rod position indicator instrument accuracy of i 12 steps. Comparison of the demand position indicators to the-bank insertion limits with verification of, rod-position by -the individual rod position indicators (after thermal soak following rod motion below 50 percent of.

RATED THERMAL POWER) is sufficient verification that the control rods are above the insertion limits.

NORTH ANNA UNIT 2 B 3/4 14 Amendment No. 121, l

- _..-__~ -.- ----.- _ - _ _ _ _ -. _ _ _ _ _

i.

L BASES (OWnued) w i

i l

The ACTION statements which permit limited variations from the basic requirements are accompanied by additional restrictions which ensure that the original design criterla are met.

Misalignment of a rod requires measurement of peaking factors or a restriction in THERMAL POWER; either of these restrictions provides assurance of fuel rod integrity during continued operation, in addition, those accident analyses affected by a misaligned rod are reevaluated to confirm that the results remain valid during future operation.

Continuous monitoring of rod position with respect to insertion limits and rod deviation is

~

provided by the rod insertion limit monitor and rod position deviation monitor, respectively.

OPERABluTY of the rod position deviation monitor is verified by a functional test at least once per 7 days and by comparison of the indicated positions versus the respective demand position indicators at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months . If the rod position deviation monitor or the rod insertion limit monitor is inoperable, the frequency of manual comparison of indicated rod (or bank) position is increased to an interval of at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

. The maximum rod drop time restriction is consistent with the assumed rod drop time used in the accident analyses. Measurement with Tavg it 500'F and with all reactor coolant pumps -

j' operating ensures that the measured drop times will be representative of insertion times experienced during a reactor trip at operating conditions.

I NORTH ANNA UNIT 2 B 3/4 1-4a Amendment No. 121,.

?

-_4 m--

I A

M s

1 4 sJ 3/4.10 SPECIAL TEST EXCEPTIONS BASES 3/4.10.1 SHU'00WN MARGINS This special test exception provides that a minimum amount of control rod' worth is immediately.available for reactivity control when tests are perfo:med; for control ~ rod worth measurement.

This special test exception is required-to permit the periodic verification of'the actual versus predicted-core reactivity.

condition occurring as.a result of fuel burnup or fuel cycling operations.

3/4.10.2 GROUP HEIGHT INSERTION; AND POWER-DISTRIBUTION LIMITS This special test exception permitsLindividual: control rods to be positioned.

outside of their normal group heights and insertion-limits'during the performance-of-such PHYSICS TESTS as those required to.1) measure. control rod worth'and-2) determine the reactor stability index and damping factor under xenon oscillation conditions.

i i

3/4.10.3 PHYSICS TESTS L

l L

This specirl test exception permits PHYSICS TESTS to be performed at less than.or equal 5% of RATED THERMAL POWER with the RCS T slightly lower j

thannormallyallowedso'thatthefundamentalnuclearchaflEteristicsofthe r

reactor core and related instrumenta!

oan be verified.

Inl order for?various characteristics tc be accurately me;;; red, it is, at times, necessary to operate outside the normal restricisons of these Technical-Specifications.

For instance, to measure the moderator temperature coefficient at BOL, it is necessary to position the various co trol rods'at heights which may not

.l normally be allowed by Specification 3.1.3.6 which may'in turn cause the RCS T,yg to fall slightly below the minimum temperature of Sperification 3.1.1.5.

3/4.10.4 REACTOR COOLANT LOOPS This special test exception permits-reactor criticality under no flow conditions and is required to perform certain startup and PHYSICS TESTS while'_

at low THERMAL POWER levels.

J i

1 NORTH ANNA --UNIT 2 8 3/4 10-1

. Amendment No. 121,

.

ML20059G337

Text

Attachment:

Attachment:

Navigation menu

Search