ML20034H671

Amends 175 & 174 to Licenses DPR-32 & DPR-37,respectively, Allowing Entry Into Action Statement Due to Missed Surveillance to Be Delayed for 24 H

ML20034H671
Person / Time
Site:	Surry
Issue date:	03/12/1993
From:	Berkow H Office of Nuclear Reactor Regulation
To:
Shared Package
ML20034H672	List: ML20034H671
References
NUDOCS 9303190211
Download: ML20034H671 (28)

Text

l

.]

~

[go ana

'o UNITED STATES o

~

NUCLEAR REGULATORY COMMISSION

{

E WASHINGTON, D. C. 20555 o

%, +... /'

]

l VIRGINIA ELECTRIC AND POWER COMPANY DOCKET NO. 50-280 SURRY POWER STATION. UNIT NO. 1 ei I

AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.175 License No. DPR-32 P

1.

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

(the licensee) dated August 4,1992, as supplemented January-14,

.A.

The application for amendment by Virginia Electric and Power Company-~

j 1993, complies with the standards and. requirements of the Atomic i

s Energy Act of 1954, as amended (the Act) and the Commi.ssion's rules-

-l and regulations set forth.in 10 CFR Chapter I, B.

The facility will operate in conformity'with the app'lication, the provisions of the Act, and the rules and-regulations of the Commission; C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without~ endangering the health and safety of the public, and (ii) that such activities will be i

conducted in compliance with the Commission's regulations; l

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 i

E.

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

1 i

1 i

'9303190211 930312 PDR. ADOCK 05000280 p

PDR

-,,-y 9,.-.-

e

. 2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.B of Facility Operating License No. DPR-32 is hereby amended to read as follows:

(B) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 175, are hereby incorporated in the license.

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

3.

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

FOR THE NUCLEAR REGULATORY COMMISSION erbert N. Berkow, Director Project Directorate 11-2 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: March 12, 1993

i p etouq

., i t

UNITED STATES I

i l.

N E

NUCLEAR REGULATORY COMMISSION

(

l[

WASHINGTON, D.C. 20555 @ 01

/

a...*

VIRGINIA ELECTRIC AND POWER COMPANY DOCKET NO. 50-281 SURRY POWER STATION. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 174 4

License No. DPR-37 1.

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

A.

The application for amendment by Virginia Electric and Power Company (the licensee) dated August 4,1992, as supplemented January 14, 1993, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; t

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 Commission's regulations; i

i D.

The issuance of this amendment will not be inimical to the common j

defense and security or to the health and safety of the public; and E.

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

i

. 2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.B of Facility Operating License No. DPR-37 is hereby amended to read as follows:

(B) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.174, are hereby incorporated in the license.

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

3.

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

FOR THE NUCLEAR REGULATORY CCMMISSION I

r Herbert N. Berkow, Director Project Directorate 11-2 Division of Reactor Projects - 1/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: March 12, 1993 l

1

^-

t ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO. 175 TO FACILITY OPERATING LICENSE NO. DPR-32 AMENDMENT NO. 174 TO FACILITY OPERATING LICENSE NO. OPR-37 DOCKET NOS. 50-280 AND 50-281 Revise Appendix A as follows:

Remove Paoes Insert Paaes TS 3.12-3 TS 3.12-3 TS 3.12-4 TS 3.12-4 TS 4.0-1 TS 4.0-1 TS 4.0-2 TS 4.0-2 TS 4.0-3 TS 4.0-3 TS 4.0-4 TS 4.0-4 TS 4.0-5 TS 4.0-6 TS 4.0-7 TS 4.0-8 1

TS 4.1-6 TS 4.1-6 TS 4.1-8b TS 4.1-8b TS 4.1-9b TS 4.1-9b TS 4.2-1 TS 4.2-1 1

TS 4.4-2 TS 4.4-2 TS 4.5-1 TS 4.5-1 TS 4.5-2 TS 4.5-2 TS 4.7-1 TS 4.7-1 TS 4.8-1 TS 4.8-1 TS 4.8-2 TS 4.8-2 TS 4.10-1 TS 4.10-1 TS 4.11-1 TS 4.11-1 TS 4.17-1 TS 4.17-1 i

i

TS 3.12-3 B.

Power Distribution Limits 1.

At all times except during low power physics tests, the hot channel j

factors defined in the basis meet the following limits:

i Fo(Z) s 2.32/P x K(Z) for P > 0.5 Fo(Z) s 4.64 x K(Z) for P s 0.5 F"s s 1.56 [1 + 0.3 (1-P)] for three loop operation 3

s 1.55 [1 + 0.2 (1-P)) for two loop operation where P is the fraction of RATED POWER at which the core is l j

operating, K(Z) is the function given in TS Figure 3.12-8, and Z is the core height location of FO.

l 2.

Prior.to exceeding 75% power following each core loading and during each effective full power month of operation thereafter, j

power distribution maps using the movable detector system shall be i

made to confirm-that the hot channel factor limits of this specification are satisfied. Forthe purpose of this confirmation:

The measurement of total peaking factor F$'** shall be a.

increased by eight percent to account for manufacturing tolerances, measurement error and the effects of rod bow.

The measurement of enthalpy rise hot channel factor F"s l 3

shall be compared directly to the limit specified in Specification 3.12.B.1. If any measured hot channel factor exceeds its limit specified under Specification 3.12.B.1, the reactor power and high neutron flux trip setpoint shall be l

reduced until the limits under Specification 3.12.B.1 are met.

If the hot channel factors cannot be brought to within the limits of Fo(Z) s 2.32/P x K(Z) and da s 1.56 within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, the Overpower AT and Overtemperature AT trip setpoints shall be similarly reduced.

b.

The provisions of Specification 4.0.4 are not applicable.

Amendment Nos.175 and 174

.. a

j TS 3.12-4

{

l 3.

The reference equilibrium indicated axial flux difference (called the

]

target flux difference) at a given power level Po is that indicated -

i axial flux difference with the core in equilibrium xenon conditions l

(small or no oscillation) and the control rods more than 190 steps

- withdrawn. The target flux difference at any other power level P is

,i equal to the target value at Po multiplied by the ratio P/Po. The target flux difference shall be measured at least once per equivalent full power quarter. The target flux difference must be updated during each effective full power month of operation either by actual measurements or by linear interpolation using the most recent value and the value predicted for the end of the cycle life. The provisions of Specification 4.0.4 are not applicable.

i

- i 4.

Except as modified by. Specifications 3.12.B.4.a b, c, or d below, the indicated axial flux difference shall be maintained within a i S%

band about the target flux difference (defines the target cand on axial flux difference).

a.

At a power level greater than 90 percent of rated power, if the indicated axial flux difference deviates from its target a

band, within 15 minutes either restore the indicated axial flux difference to within the target band or reduce the reactor i

power to less than 90 percent of RATED POWER.

b.

At a power level no greater than 90 percent of RATED

POWER, (1) The indicated axial flux difference may deviate from its target band for a maximum of one hour (cumulative) in-any 24-hour period provided the flux difference is within the limits shown on TS Figure 3.12-10.

Amendment Nos. 175 and 174

~

TS 4.0-1 l

i 4.0 SURVElLLANCE REQUlREMENTS i

Surveillance requirements provide for testing, calibrating, or inspecting l 4.0.1 i

those systems or components which are required to assure that operation

'l of the units or the station will be as prescribed in the preceding sections.

4.0.2 Surveillance requirement specified time intervals may be adjusted plus or [

{

minus 25 percent to accommodate normal test schedules.

i 4.0.3 Failure to perform a surveillance requirement within the allowed surveillance interval, defined by Specification 4.0.2, shall constitute noncompliance with the operability requirements for a Limiting Condition i

for Operation. The time limits of the Action Statement requirements are I

applicable at the time it is identified that a surveillance requirement has not been performed. The Action Statement requirements may be delayed for up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to permit the completion of the surveillance when the allowable outage time limits of the Action Statement requirements are less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Surveillance requirements do not have to be performed on inoperable equipment.

i 4.0.4 Entry into an operational condition shall not be made unless the surveillance requirement (s) associated with a Umiting Condition of Operation has been performed within the stated surveillance interval or as otherwise specified. This provision shall not prevent passage through or i

to operational conditions as required to comply with Action Statement requirements.

Amendment Nos. 175 and 174

i TS 4.0-2 A

4.0.5 Surveillance requirements for inservice inspection and testing of ASME Code Class 1,2, and 3 components shall be applicable as follows.

d d

Inservice inspection of ASME Code Class 1,2, and 3 components

,j a.

and inservice testing of ASME Code Class 1,2, and 3 pumps and valves shall be performed in accordance with'Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by 10 CFR 50, Section 50.55a(g), except where i

specific written relief has been granted by the Commission l

pursuant to 10 CFR 50, Section 50.55a(g)(6)(i).

b.

Surveillance intervals specified in Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda for the inservice inspection and testing activities required by the ASME f

Boiler and Pressure Vessel Code and applicable Addenda shall be applicable as follows in these Technical Specircations:

Amendment Nos.175 and 174

i TS 4.0 ASME Boiler and Pressure Vessel Code and Applicable Required Frequencies Addenda Terminology for for Performing inservice inspection and inservice inspection Testina Activities and Testino Activities j

i Monthly At least once per31 days Quarterly or Every 3 months At least once per 92 days COLD SHUTDOWN At least once per CSD REFUELING SHUTDOWN At least once per RSD f

The provisions of Specification 4.0.2 are applicable to the above c.

required frequencies for pump and valve testing only. Extensions for inservice inspection of components will be to the requirements of Section XI of the ASME Boiler and Pressure Vessel Code.

d.

Performance of the above inservice inspection and testing activities shall be in addition to other specified Surveillance Requirements.

f e.

Nothing in the ASME Boiler and Pressure Vessel Code shall be construed to supersede the requirements of any Technical Specification.

i Amendment Nos. 175 and 174

=

I.

TS 4.0-4 BASES

-l 4.0.1 This specification provides that surveillance activities necessary to ensure the Limiting Conditions for Operation are met and will be performed during all operating conditions for which the Limiting Conditions for Operation are applicable.

4.0.2 The provisions of this_ specification provide allowable tolerances for performing surveillance activities beyond those specified in the nominal surveillance interval.

These tolerances are necessary to provide 1

operational flexibility because of scheduling and performance considerations. The phrase "at least" associated with & surveillance i

frequency does not negate this allowable tolerance value and permits the performance of more frequent surveillance activities.

l 4.0.3 This specification establishes the failure to perform a Surveillance Requirement within the allowed surveillance interval, defined by the provisions of Specification 4.0.2, as a condition that constitutes a failure to meet the operability requirements for a Limiting Condition for Operation. Under the provisions of this specification, systems and components are assumed to be OPERABLE when surveillance requirements have been satisfactorily performed within the specified time Interval. However, nothing in this provision is to be construed as implying that systems or components are OPERABLE when they are found or known to be inoperable although still meeting the surveillance requirements. This specification also clarifies that the Action Statement requirements are applicable when Surveillance Requirements have not I

been completed within the allowed surveillance interval and that the time limits of the Action Statement requirements apply from the point in time it Amendment Nos. 175 and 174

=.

TS 4.0-5 is identified that a surveillance has not been po'rformed and not at the time that the allowed surveillance interval was exceeded. Completion l

of the surveillance requirement within the allowable outage time limits of the Action Statement requirements restores compliance with the i

requirements of Specification 4.0.3. However, this does not negate the fact that the failure to have performed the surveillance within the allowed surveillance interval, defined by the provisions of Specification 4.0.2, was a violation of the operability requirements of a Limiting

- Condition for Operation. Further, the failure to perform a surveillance l

within the provisions of Specification 4.0.2 is a violation of a Technical Specification requirement and is, therefore, a reportable event under.

i the requirements of 10 CFR 50.73(a)(2)(i)(B) because'it is a condition prohibited by the plant's Technical Specifications.

1 If the allowable outage time limits of the Action Statement requirements i

are less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or a shutdown is required to comply with Action Statement requirements, e.g., Specification 3.0.1, a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> allowance' is provided to permit a delay in implementing the Action Statement requirements. This provides an adequate time limit to complete surveillance requirements that have not been performed. The purpose of this allowance is to permit the completion of a surveiliance before a shutdown is required to comply with Action Statement requirements or before other remedial measures would be required that may preclude completion of a surveillance. The basis for this allowance includes consideration for plant conditions, adequate planning, availability of personnel, the time required to perform the surveillance, and the safety significance of the delay in completing the required surveillance. This Amendment Nos. 175 and 174

f TS 4.0-6 '

I provision also provides a time limit for the completion of surveillance requirements that become applicable as a consequence of condition changes imposed by Action Statement requirements and for completing surveillance requirements that are applicable when an exception to the

'i requirements of Specification 4.0.4 is allowed. If a surveillance is not l

completed within the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> allowance, the time limits of the Action Statement requirements are applicable at that time. When a surveillance is performed within the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> allowance and the surveillance 3

i requirements are not met, the time limits of the Action Statement requirements are applicable at the time that the surveillance is terminated.

i t

i Surveillance requirements do not have to be performed on inoperable j

equipment because the Action Statement requirements define the i

remedial measures that apply. However, the surveillance requirements have to be met to demonstrate that inoperable equipment has been restored to OPERABLE status.

4.0.4 This specification establishes the requirement that all applicable surveillances must be met before entry into an operational condition spooified in the applicability statement. The purpose of this specif~ ation c

is to ensure that system and component operability requirements or parameter limits are met before entry into a condition for which these systems and components ensure safe operation of the facility. This provision applies to changes in operational conditions associated with plant shutdown as w911 as startup.

Amendment Nos. 175 and 174 l

TS 4.0-7 t

i Under the provisions of this specification, the applicable surveillance 4

requirements must be performed within the specified surveillance ' interval f

to ensure that the Umiting Conditions for Operation are met during initial plant startup or following a plant outage.

I i

'y Exceptions to Specification 4.0.4 allow performance of surveillance

[

requirements associated with a Limiting Condition for Operation after i

entry into the applicable operational condition.

i When a shutdown is required to comply with Action Statement i

requirements, the provisions of Specification 4.0.4 do not apply because f

this would delay placing the facility in a lower condition of operation.

1 4.0.5 This specification ensures that inservice inspection, repairs, and l;

replacements of ASME Code Class 1, 2, and 3 components and inservice testing of ASME Code Class 1,2, and 3 pumps and valves will i

i be performed in accordance with a periodically updated version of Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by 10 CFR 50 Section 50.55a. Specific relief from l

i portions of the above requirements has been provided in writing by the Commission and is not a part of these Technical Specifications.

This specification includes a clarification of the frequencies for performing the inservice inspection and testing activities required by Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda.

This clarification is provided to ensure consistency in surveillance intervals throughout these Technical Specifications and to remove any ambiguities relative to the frequencies for performing the I

required inservice inspection and testing activities.

Amendment Nos.175 and 174

1 3

TS 4.0-8 l Under the terms of this specification, the more restrictive requirements of the Technical Specifications take precedence over the ASME Boiler and Pressure Vessel Code and applicable Addenda. For example, the Technical Specification definition of OPERABLE does not grant a grace l

5 period before a device that is not capable of performing its specified function is declared inoperable and takes precedence over the ASME Boiler and Pressure Vessel Code provision which allows a valve to be incapable of performing its specified function for up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> before i

being declared inoperable.

i i

i i

f Amendment Nos. 175 and 174 1

yc A:.&

n N

N N

W O

)X O

IT T

D d

A A

H ra Rn Rn n

rf l

o xBo o

d oo nEi n

H n

n r

s l it so ole ela it ara)f

)

a o

T,S s

)

El nt eAc npeAc ipe c

i sWatepea t

n t

r r

h of ioOB c

c r

e bCh orbCn i

a=

t, b L E

ca mo Ht c O e p, b e t e

da it s

c t

t aE pyL e N yL e N t

c O k

y mme c p, m N S e man eN du aEp=

n r

d mN S e=

T o o aiC nPl a

a bo ay m N S r=

p o

r aDatshbr sNf i lb m

e r s esR s sNf l e A et A

sf l

l i i

s h

a t

c l

e rAop doAop la rH op e e or bro f

r i

e Es t

R b

r Tidr ec e

ao o

a boe sn t H s =p

(

p oC p

r t

otHs=

nt scE t t n sg taA c Nsa u

wf i cCn t

t isr cCn r

T ueg emOoo ibaT n

o t

e R ; e,looe f

e o

e o

a t

t rA odlo eIA b e, tvemio i T

%Avdia emio l

t cemIi t

t h

e c n mrD cb sn sn adit s n p u leneRor m pi a a5t isnr daive

idaive dAive l

o nE s

le snhor a s a :n. m e t i

v nhor e

xe n

t 1 eid e o h M amr. omodr a viodr a s

r a e s

emr a p4 bolu B p4 r i t

l s

ne a p4 hnichwR e

r r

at k I t

r wnr l

D ia t

xgep-,es ude0 t c evd E t

ge ude0 u Le0 e hiaheoAT ts c

A a S (p p yh y e u hsNcT4 L(NcT4 BNeCT4 OC WEwsRNN gti ieaAh opeuh r

v ;

N i

i Ust A

)

)

)

)

)

)

)

)

))

)

))

))

))

1 2

3 4

5 1

2 3

12 3

12 12 34 SN O

ITA S R L B

l E

l N t

)

)

)

))

)

s 2

1 1

1 2 A N e

(

3 M M M M

(

(

((

T M

P P

MM M(

C A

. H K C C

1 E T 1

H N 4 C E

e t

))

)

)

M a

)

E R w

5,5,4 3,

3 U

d 1 3(

2 2

R R R R H R L

O l

DO R

R

((R

(

(

R a

B F

C A

T T.

S S E N I

I C F N O k

E

)

c U T e

S S

S S

S S S A.

2, )

h 1(4 Q S N

S(

p E E R T F

MU M

IN IM

)

q w

n o

h L

n e

y n

e r

c g

u t

h c ae n

a ig ne a

r l

D R

e p

v

(

q e

e H u e

l g

e )t g

m w e e e e

o an e

o L r

r n

n a

ia e n )t n

n t

l u F o T

F e s d r

a R

dp Rio ea t

t t

s n lm h

e r

e ep n

n a e a o C

e ms c e e

a a

WP P

r r

r i

l e

w e0 u s o

o r

r g d o

n-o4 o

o e e a o t 1 P

P SP C

C a t

t R

i d

ir o

r r

r r

r e

aw

= w o

o u u V g e

e o

=o s

t e s o

l c

c s s V d

cl l

l l

e ee a

a e e K na u

ub i b e

e r

r N

N(

N(

R R P P 4 A 1

2.

3 4.

5.

8.

7 8 9 3$ge@*r k',_U k da

TABLE 4.1-1 (Continued)

MINIMUM FREQUENCIES FOR CHECK. CAllBRATIONS AND TEST OF INSTRUMENT CHANNELS l

Channel Deandqlina Check Cahbrata lag Ramasks

39. Steem/Feedwater Flow and Imw 84 S

R M(1)

1) The provisions of Specslication 4.0.4 Wmw Level are not apphcable

40. Inteke Canallow (See Footnote 1)

D R

M(t ).

1) Logic Test O(2)

2) Channel Elodronics Test

41. TuMne Trip and Foodweser =al=aian n

a. Steam generator waser level high S

R M

b. Automatic actuation logic and N.A.

R M(1)

1) Automatic eduation logic only, adussion relay aduation relays tested each refueling

42. Reactor Trip System Interlocks

a. IrArmedete range neutron N.A.

R(1)

M(2,3)

1) Neutron detectors may be escluded from Iksi P4 the calibration

b. Low toador trips block, P-7 N.A.

R(1)

M(2,3)

2) With power greater than or equal to the

• d'** * '

c. Power range neutron flux, P-8 H.A.

R(0 M(2.3) consist M ini is

d. Power range nowron flux, P-10 H.A.

9(1)

M(2.3) h the required state by observing the perrmosive annuncessor unndow a

e. TuMne impulse preneure N.A.

R R

3) The provisions of Spoohcation 4.0.4 1

g are not apparad=

to 5

E

~

tn g

Footnote 1:

o.

Check Consists of verifying for an irwhcased irdake canallevel greater than 23*4' that at four low level sensor channel alarms are a

not in en alarm state.

Cahbrmann Consists of uncovering the level sensor and measuring the time response and voltage signals for the immersed and dry smndeons

-(

it also verifies the proper adion of instrument channel from sensor to electronics to channel output releys and annunciator Only (O

the two avaslable sensors on the shutoown unit would be tested.

,A Tests

1) The logic test venties the three out of four logic development for each train by using the channel test switches for that train.

y

2) Channel electronics test venfies that electronics module responds properly to a superimposed defferential millivoit signal oo U

which is equivalent to the sensor detoding a " dry

• corxlition.

TABLE 4.1-2A l

TESTS I

FSAR Section Descreten last Frenuancy Reference

1. ControlRod Assembles Rod drop times of all Prior to reactor criticality:

7 fun length rods at

a. For aN rods foNounng each removal hot conditions of the reactor vessel head,

b. For speciaNy affected individual rods following any maintenana on or modi-fication to the control rod drive system which could afled the drop time of those specife rods, and

c. Each REFUELING SHUTDOWN l

2. ControlRod Assembhos Partial movement of Every 2 weeks 7

aN rods

3. Refueling Water Chemimi Functional Each REFUELING SHUTDOWN 6

Addition Tank

4. Pressurizer Safety Vahs Setpoint Per TS 4.0.3 4

5. Main Steam Safety Valves Setpoint Per TS 4.0.3 10

6. Containment isolesion Trip

' Functional Each REFUELING SHUTDOWN 5

g

7. Refueling System interlocks

• Functional Prior to refueling 9.12

8. Service Water System

• Functional Each REFUELING SHUTDOWN 9.9

9. Fire Proteden Pump and Functional

_ Monthly 9.10 re -

Power Supply f

10. Primary System Leakage

• Evoluate Daily 4

11. DieselFuelSupply

• Fuel inventory 5 days / week 8.5 E

12.- Boric Acid Pipeg Heat

' Operational Monthly 9.1 Tracing Cercues o,

-.g o

13. Main Steam Line Trip Functional Before sech startup (TS 4.7) 10 Co y

Valves

- (Fun Closure)

The provisions of Specification

,a 4.0.4 are not applicable.

y so

TS 4.2-1 4.2 AUGMENTED INSPECTIONS Applicability Applies to inservice inspections which augment those required by ASME Section XI.

Objective i

To provide the additional assurance necessary for the continued integrity of important components involved in safety and plant operation.

Soecifications A.

Inspections shall be performed as specified in T.S. Table 4.2-1.

Nondestructive examination rechniques and acceptance criteria shall be in compliance with the requirements of TS 4.0.5.

B.

The normalinspection intervalis 10 years.

C.

Detailed reccrds of each inspection shall be maintained to allow a continuing evaluation and comparison with future inspections.

l i

Bases l

The inspection program for ASME Section XI of the ASME Boiler and Pressure Vessel Code limits its inspection to ASME Code Class 1,2, and 3 components and supports. Certain components, under Miscellaneous inspections in this section, were added because of no corresponding code requirement. This added requireraent provides the inspection necessary to insure the continued integrity of those components.

Aniendment Nos.175 and 174 i

TS 4.4-2 i

b.

The leakage rate test will be performed at a pressure of at least 39.2 psig (Pa)-

c.

The measured leakage rate Lam shall not exceed 75% of the design basis accident leakage rate (La) of 0.1 weight percent per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at pressure Pa-Type B and C tests will be performed at a pressure 2.

(Pa) in accordance with the provisions of Appendix J, Section Ill.B and C.

l Also. within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> after use of the personnel airlock, the seals will be tested at least at the peak calculated accident pressure to verify that they are properly sealed.

C.

Acceptance Criteria Type A, B, and C tests will be considered to be satisfactory if the acceptance criteria delineated in Appendix J, Sections lil.A.5(b),111.B.3, and Ill.C.3 are met.

D.

Retest Schedule The retest schedules for Type A, B, and C tests will be in accordance with Section Ill.D of Appendix J.

E.

Inspection and Reporting of Tests inspechon and reporting of tests will be in accordance with Section V of Appendx J.

F.

The provisions of Specification 4.0.2 are not applicable.

Amendment Nos. 175 and 174

I

}

TS 4.5-1 l

j l

4.5 SPRAY SYSTEMS TESTS i

i

\\

[

AnpEcability j

Applies to the testing of the Spray Systems.

]

1

(

Objective 4

i

[

To verify that the Spray Syn,tems will respond promptly and perform their i

j design function,if required.

)

i

}

Soecification l

A.

Each containment spray subsystem shall be demonstrated 1

l-OPERABLE:

l 1

1.

By verifying, that on recirculation flow, each containment

)

spray pump performs satisfactorily when tested in i

accordance with Specification 4.0.5.

t 2.

By verifying that each motor-operated valve in the 1

containment spray flow path performs satisfactorily when j

I tested in accordance with Specification 4.0.5.

j 3.

At least once per 5 years, coincident with the closest refueling outage, by perfonning an air or smoke flow test and verifying each spray nonle is unobstructed.

4.

Coincident with the containment spray pump test described in Specification 4.5.A.1, by verifying that no paniculate material clogs the test spray nonlos in the refueling water storage tank.

4 B.

Each recirculation spray subsystem shall be demonstrated l

OPERABLE:

1.

By verifying each recirculation spray pump performs satisfactorily when tested in accordance with Specification

\\

4.0.5.

-Amendment Nos. 175 and 174

TS 4.5-2 2.

By verifying that each motor-operated valve in the recirculation spray flow paths performs satisfactorily when tested in accordance with Specification 4.0.5.

3.

At least once per 5 years, coincident with the closest refueling outage, by performing an air or smoke flow test and verifying each r

spray nozzle is unobstructed.

4.

At least once each refueling outage by verifying that total system uncollected leakage from valves, flanges, and pumps located outside containment does not exceed 964 cc/hr.

C.

Each weight-loaded check valve in the containment spray and outside containment recirculation spray subsystems shall be demonstrated OPERABLE at least once each refueling period, by cycling the valve one complete cycle of full travel and verifying that each valve opens when the discharge _line of the pump is pressurized with air and seats when a vacuum is applied.

D.

A visualinspection of the containment sump and the inside containment recirculation spray pump wells and the engineered safeguards suction inlets shall be performed at least once each refueling period and/or after major maintenance activities in the containment. The inspection should verify that the containment sump and pump wells are free of debris that could degrade system operation and that the sump components (i.e., trash racks, screens) are properly installed and show no sign of structural distress or excessive corrosion.

Ba$il The flow testing of each containment spray pump is performed by opening the normally closed valve in the containment spray pump recirculation line returning water to the refueling water storage tank. The containment spray pump is operated and a quantity of water recirculated to the refueling water storage tank. The discharge to the tank is divided into two fractions, one for the major portion of the recirculation flow and the other to pass a small quantity of water through test nozzles which are identical with those used in the containment spray headers. The purpose of the recirculation through the test nozzles is to assure that there are no particulate materialin the refueling water j

storage tank small enough to pass through pump suction strainers and largs enough to clog spray nozzles.

Amendment Nos. 175 and 174

TS 4.7-1 l

4.7 - MAIN STEAM LINE TRIP VALVES i

I Applicability Applies to periodic testing of the main steam line trip valves.

'I Objective To verify the ability of the main steam line trip valves to close upon signal.

Specification A.

Tests and Frequencies l

1.

Each main steam line trip valve shall be tested for full closure before each startup, unless a satisfactory test has been conducted within the previous 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. The provisions of Specification 4.0.4 are not applicable.

B.

Acceptance Criteria 1.

A full closure test of a main steam line trip valve shall be considered satisfactory if the following criteria are met:

i a.

T1 less than or equal to 4.0 seconds and b.

T2 less than or equal to 5.0 seconds i

where i

Amendment Nos. 175 and 174

TS 4.8-1 4.8 AUXILIARY FEEDWATER SYSTEM i

Anoliemhility i

Applies to periodic testing requirements of the Auxiliary Feedwater System.

t Objective To verify the operability of the auxiliary steam generator feedwater pumps and their ability to respond properly when required.

I Soecification A.

Tests and Frecuencies i

1.

Each motor driven auxiliary steam generator feedwater pump shall be flow tested for at 19ast 15 minutes on a monthly basis to demonstrate its oper?sility.

2.

The turbine driven auxiliary steam generator feedwater pump shall be flow tested for at least 15 minutes on a monthly basis to demonstrate its operability. The provisions of Specification 4.0.4 are not applicable.

l 3.

The auxiliary steam generator feedwater pump discharge valves shall be exercised on a monthly basis.

l l

l l

Amendment Nos. 175 and 174

l i

TS 4.8-2 l

1 I

4a. Within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> prior to temperature and pressure exceeding 350'F l

and 450 psig respectively, the motor driven auxiliary feedwater pumps shall be flow tested from the 110,000 gallon above ground condensate storage tank to the steam generators.

4b. Within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> after achieving reactor criticality, the steam turbine l

driven auxiliary feedwater pump shall be flow tested from the 110,000 gallon above ground condensate storage tank to the steam l

generators. The provisions of Specification 4.0.4 are not applicable.

t l

i 5.

During periods of extended reactor shutdown, the testing requirements of Specification A.1, 2, and 3 may be modified as follows:

i a.

Only one of the three auxiliary steam generator feedwater pumps shall be flow tested for at least 15 minutes on a monthly basis to demonstrate its operability provided the required components are tested prior to startup.

b.

The auxiliary steam generator feedwater pump discharge valves of the pump tested in 5a shall be exercised on a monthly basis provided all the discharge valves are tested prior to startup.

B.

Acceptance Cntena These tests, except the system flow test, shall be considered satisfactory if control board indication and subsequent visual observation of the equipment demonstrate that all components have operated and sequenced properly.

Amendment Nos.175 and 174

TS 4.10-1 4.10 REACTIVITY ANOMAllES Acolicability l

Applies to potential reactivity anomalies.

'j Obiective To require evaluation of applicable reactivity anomalies within the reactor.

Scecificction A.

Following a normalization of the computed boron concentration as a function of bumup, the actual boron concentration of the coolant shall be I

compared monthly with the predicted value. If the difference between the observed and predicted steady-state concentrations reaches the equivalent of one percent in reactivity, an evaluation as to the cause of the discrepancy shall be made and reported to the Nuclear Regulatory Commission per Section 6.6 of these Specifications. The provisions of Specification 4.0.4 are not applicable.

B.

During periods of POWER OPERATION at greater than 10% of RATED POWER, the hot channel factors identified in Section 3.12 shall be determined during each effective full power month of operation using l

data from limited core maps, if these factors exceed their limits, an j

evaluation as to the cause of the anomaly shall be made. The provisions of Specification 4.0.4 are not applicable.

Amendment Nos. 175 and 174 l

1 TS 4.11e1 r

4.11 SAFETY INJECTION SYSTEM TESTS i

AnpEcabihty i

Applies to operational testing of the Safety injection System.

i Objective

,l l

To verify that the Safety injection System will respond promptly and perform its design functions, if required.

a Soecification A.

The safety injection system shall be demonstrated OPERABLE:

1.

By verifying, that on recirculation flow, each low head safety injection pump performs satisfactorily when tested in accordance with Specification 4.0.5.

2.

By verifying, that on recirculation flow, each charging pump

)

performs satisfactorily when tested in accordance with Specification 4.0.5.

3.

By verifying that each motor-operated valve in the safety injection flow path performs satisfactorily when tested in accordance with Specification 4.0.5.

4.

At least once per 18 months, during shutdown, by:

a.

Verifying that each automatic valve in the flow path actuates to its correct position on a safety injection test signal. The charging and low head safety injection pumps may be immobilized for this test.

b.

Verifying that each of the charging and safety injection pump circuit breakers actuate to its correct position on a safety injection test signal. The charging and low head safety j

injection pumps may be immobilized for this test.

l Amendment Nos. 175 and 174 l

TS 4.17-1 4.17 SHOCK SUPPRESSORS (SNUBBERS)

Acolicability Applies to all hydraulic and mechanical shock suppressors (snubbers) which are required to protect the Reactor Coolant System and other safety-related systems. Snubbers excluded from this inspection are those installed on non-safety-related systems and then only if their failure or failure of the system on which they are installed would have no adverse effect on any safety-related system.

Obiective To specify the minimum frequency and type of surveillance to be applied to the hydraulic and mechanical snubbers required to protect the Reactor Coolant System and other safety-related systems.

Soecification Each snubber shall be demonstrated OPERABLE by performing the following augmented inservice inspection program and the requirements of Specification J

4.0.5. As used in this specification," type of snubber'shall mean snubbers of the same design and manufacturer, irrespective of capacity.

A.

VisualInsoections

1. Snubbers are categorized as inaccessible or accessible during reactor operation. Each of these categories (inaccessible and accessible) may be inspected independently according to the schedule determined by Table 4.17-1. The visualinspection interval of each category of snubber shall be determined based upon the-criteria provided in Table 4.17-1.

Amendment Nos. 175 and 174

-.