Text

Amends 135 & 114 to Licenses DPR-70 & DPR-75,respectively, Incorporating Portion of Westinghouse Owners Group Topical Rept WCAP-10271 That Provides for Longer Surveillance Intervals
	ML20118A401
Person / Time
Site:	Salem
Issue date:	08/28/1992
From:	Calvo J; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20118A402	List: ML20118A401; ML20118A403;
References
	NUDOCS 9209040215
	Download: ML20118A401 (12)
	v • d • e

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n,,.... p PUBLIC SERVICE ELECTRIC & GAS COMPAN'I PHILADELPHIA ELECTRIC COMPANY DELMARVA POWER AND LIGHT COMPANY ATLAPTIC CITY ELECTRIC COMPANY DOCKET NO 50-272 LA1EM NUCLEAR GENERATING STATION. UNIT NO. l_

AMJMLMENT TO FACILITY ODERATING LKMSl Amendment No.135 License No. OPR-70 1.

The Nuclear Regulatory Commission (the Commission or the NRC) nas found that:

A.

The application for amendment filed by the Public Service Electric &

Gas Company, Philadelphia Electric Company, Delmarva Power and Light Company and Atlantic City Electric Company (the licensees) dated August 26, 1992, complies with the standards and requirements of the Atomic Energy Act of 1954, as aniended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; 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, ano (ii) that such activities will be conducted in compliance with the Commission's regulations set forth in 10 CFR Chapter I; D.

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

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

2.

Accordingly, the license is amended by changes to the Technical Specifica-tions as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of facility Operating License No. DPR-70 is hereby amended to read'as follows:

l 9209040215 920828 PDR ADOCK 05000272 1

P PDR

I,_ (2) Technical Soecifications and Environmental Protection Plan The. Technical Specifications contained in Appendices A and B, as revised through Amendment No.135 arr hereby incorporated in the

-license._ The licensee shall operate the facility in accordan~ce with the Technical Specifications.

3.

This license amendment is effective as of its date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

(

)

g Jose A. Calvo, Assistant Director for Region 1 Reactors Division of Reactor Projects-- 1/11 Office of Nuclear Reactor Regulation

Attachment:

-Changes to the-Technical Specifications Date of issuance:

August 28, 1992 l

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i ATTACHMENT T0 LICENSE AMENDMENT NO.135 i

FAClllTY OPERATING llCENSE NO. OPR-70 DOCKET NO. 50-272 Revise Appendix-A as follcws:

-Bgmove Paces ~

Insert Paoes 3/4 3-3 3/4 3-3 3/4 3-6 3/4 3-6 3/4 3-11 3/4 3-11 a

e

+

'O 7ABLE 3.3-1 fContinuedi f

PEACTOR TRIP SYSTEM INSTRUMENTATION s

MINIMUM re TOTAL MUMBER CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT OF CHAMMELS TO TRIP OPERABLE

. MODES ACTION 11.

Pressurizer Water Level--High 3

2 2

.1,2 6#

12.

Loos of. Flow - Single Loop, 3/ loop

~ 2/ loop in 2/ loop in 1

7#

(Above P-8) any oper-each oper-ating loop ating loop 13.

Loos of Flow - Two Loops 3/ loop 2/ loop.in 2/lciop in 1

7#.

(Above P-7 and below P-8) two oper-each oper-sting loops ating loop 14.

Steam Generator Water Level--

3/ loop 2/ loop in 2/ loop in 1,2 7#

w1 Low-Low any oper-each oper-ating loops ating loop w

l, 15.

Steam /Feedwater Flow Miematch 2/ loop-level 1/ loop-level 1/ loop-level 1,2 7#

and Low Steam Generator Water and 2/ loop-coincident and 2/ loop-Level flow mismatch with flow mismatch 1/ loop-flow cr 2/ loop-mismatch in level and eame loop 1/ loop-flow mismatch 16.

Undervoltage - Reactor 4-1/ bus 1/2 twice 3

1 6

Coolant Pumpe 17.

Underfrequency - Reactor 4-1/ bus 1/2 twice 3

1 6

Coolant Psampe a

L TABLE 3. 3 - l' fcentinued)

With the number of channels OPERABLE one-1s ts than required ACTION 3 by the _ Minimum Channels _ OPERABLE requirement and with the

.S THERMAL POWER levelt a.

.Below P-6, restore the inoperable channel to CPERABLE status prior to increasing THERMAL POWER above the P-6 Set point.

t b.

Above P-6 but below-$% of RATED THERMAL POWER, restore the inoperable channel to OPERABLE status prior to increasing THERHAL POWER above 5% of RATED THERKAL POWER.

c.

Above 5% of RATED THERMAL POWER, POWIR OPERATION may continue.

ACTION 4 -

With the number of channels OPERABLE'one less than required by the Minimum Channels OPERABLE requirement and with the THERMAL POWER levels a.

Below P-C, restore the inoperable channel to CPERABLE status prior to increasing THERMAL POWER above the P-6

Setpoint, b.

Above P-6, operation may continue.

ACTION 5 -

With the number of channels OPERABLE one less than required by the Minimum Channels CPERABLE requirement, verify compliance with the SHUTDOWN MARCIN requirements of Specification 3.1.1.1 or 3.1.1.2, as applicable, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and at least once per 32 hours3.703704e-4 days 0.00889 hours 5.291005e-5 weeks 1.2176e-5 months thereafter.

ACTION 6 --

With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the following conditions are satisfied:

a.

The inoperable channel is placed in the tripped condition within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

b.

The Minimum-Channels OPERABLE requirement is met; however, the inoperable channel may be bypassed for up to,4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance testing 0f Other Channels per Specification 4.3.1.1.

ACTION.7 -

With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed u-*il performance of the next required CHANNEL FUNCTIONAL TEST provided the inoperable channel is placed in the tripped condition within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

ACTION 8 -

NOT USED SALEM - UNIT 1 3/4 3-6 Amendment No.135 I

l l

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.e I!EAC10R TitlP SYSilM INSTittlMLNTAIl0N SURVI:llt.ANCE REQt;lR[Mf NTS CilANNFL MOO [S IN Wit!:.

CllANNEL

. FUNC i l0N AL -

SililVE11.1 ANO FUNCT10NAL UNIT CilECK CALIllRAT IGN TEST AtEQuilti D.

1.

Manual Reactor Trip Switch it. A.

N.A.

S/U(9)-

N.A.

2.

Power Range, Neutron Flux 5

D(2),M(3)

M I, 2 and Q(6) 3.

Power Range, Neutron Flux, it. A.

R(6)

M 1, 2 I!igh Positive Ilate 4

Power Range,-Neutron Flux, N.A.

R(6)

M 1, 2 liigh Negative Rate m

5.

Intermediate R'nge, a

Neutron Flux S

R(6)

S/ll(l) 1, 2 and a

6.

Source Range, Neutron Flux S(7)

R(6)

M and S/U(1) 2, 3, 4, 5 a w.

7.

Overtemperature d T S

R H

I, 2' S

R H

1, 2 11. Overpower AT 9.

Pressuriz;r Pressure--Low 5

R H

1, 2 8.

10. Pressurizer Pressure--liigh S

R H

1, 2 2

A 11.

Pressurizer Water Level--liigh S

R q

I, 2 12.

Loss of Ilow - Single Loop S

11 M

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8' NUCLEAR REGULATORY COMMISSION er g

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PUBLIC SERVICE ELECTRIC & GAS COMPANY PHILADELPHIA ELECTRIC COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-311 SALEM NUCLEAR GENERATING STATION. UNIT NO. 2 AMLNDMENT TO FACillTY OPERATING LICENSE j

Amendment No. 114 License No. DPR-75 1.

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

A.

The application for amendment filed by the Public Service Electric &

Gas Company, Philadelphia Electric Company, Delmarva Power and Light Company and Atlantic ity Electric Company (the licensees) dated August 26, 1992, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; 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 (11) that such activities will be conducted in compliance with the Commission's regulations set forth in 10 CFR Chapter I; D.

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

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

2.

Accordingly, the license is amended by changes to the Technical Specifica-tions as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of facility Operating License No. DPR-75 is hereby

-amended to read as follows:

4

~

R (2) Technical Sogeifications'and Envircnmental Protection Plan i

The Technical Specifications contained in Appendices A and B, as revised through Amendment No.114, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

1 3.

This license amendment is effective as of its date of issuance.

FOR THE NUCLEAR REGULA! RY COMMISSION 7g' d.

ClvbM

?

/Jose A. Calvo, Assistant Director for Region 1 Reactors Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation

Attachment:

Changes to-the Technical Specifications Date of Issuance: August 28, 1992

r ATTACHMEt41 TO LICEt45E AMEt4QSIjii f40.116_

FAClllTY OP BATlf4G LICiliSE tJ0 DPR-75 DOCKEi tio, t'-111 Revise Appendix A as follows:

Removeflan Insert Pa.gn 3/4 3-3 3/4 3-3 3/4 3-6 3/4 3-6 3/4 3-11 3/4 3-11 G

e t

i

~~

TABLE 3.3 Jontir ydi _

PEACTOR TRIP SYSTEM INSTV M ATIcet

, U' MINIMUM TOTAL MUMBER CHANNELS CHANNELS APPLICABLE

'?

FUNCTICWAL UNIT OF CHAMMELS TO TRIP OPERABLE MODES ACTION 11.

Pressurizer water Level

'3 2

2 1,2 6 '#

-High i

12.~

Loss of Flow - Single Loop 3/ loop 2/ loop in 2/ loop in 1

7(

(Above P-8) any oper-each oper-sting loop ating loop i

. Loos of Flow'- Two Loope 3/ loop 2/ loop in 2/ loop in 1

7#

13.

1-

-(Above P-7 and below P-8) two oper-each oper-ating loops ating loop

{'

14.

Steam Generator Water 3/ loop 2/ loop in 2/ loop in 1,2 7#

Leve l-Low-Low any oper-each oper-ating loops ating loop u

i Y

15.

Steam /reedwater riow 2/ loop-level 1/ loop-level 1/ loop-level 1,2 7#

4 Hiematch and Low Steam and coincident and Generator Water Level 2/ loop-flow with 2/ loop-flow mismatch 1/ loop-flow mismatch or mismatch in 2/ loop-level I

emme loop and 1floop-flow 3

mismatch i

16.

Undervoltage-Reactor 4-1/ bus 1 *2 twice 3

1 6

Ccent Pumpe 1

17.

Underfr % w cy-Reactor.

4 1/ bus 1/2 twice 3

1 6

Coolant Pumps E.

i 3,.-

2.

c-e l

IAttr 3.3 4_fcontinuedi i

ACT20W 3 With the nunter of channels OPERABLE one less than required by the Minimtm Channels OPERABLE requirement and with the l

THERMAL POWER levelt Below P-6, restore the $noperable channel to CPERABLE t

4.

status pricr to increasing THERMAL POWER above the P-6 l

setpoint.

I b.

Above P-6, but below 5% of RATED THERMAL power, restore 5

the inoperable channel to CPERABLE status prior to

)

increasing THERKAL POWER above $% of-RATEP THERMAL POWER.

c.

Above 5% of RATED THERMAL POWER, POWER OPERATION may continue.

d.

Above 10% of RxTED THERMAL POWER, the provisions of specification 3.0.3 are not applicable.

~

ACTION 4 With the number of channels OPERABLE one less than required I

by the Minimum Channels OPERABLE requirement and with the THERMAL POWER levelt I

a.

Below P-6, restore the inoperable channel to OPERABLE status prior to increasing THERMAL POWER above the P-6 Setpoint.

b.

Above P-6, operation may continue.

ACTION $

With the number of channels OPERABLE one less than required by_ the Minimum Channels OPERABLE requirement, verify compliance with the $HUTDOWN KARGIN requirements of specification 3.1.1.1 or 3.1.1.2, as applicable, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter.

+

ACTION 6 With t!t', number of OPERABLE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the following conditions are satisfied a.

The inoperable channel is placed in the tripped condition within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , b.

The Minimum Channel CPERABLE requirement le met; however, the inoperable channel may be bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance -testing of Other channels per Specificatico 4.3.1.1.

ACTION 7 With the number of OPERABLE channels one less than the

-Total' Number _of Channels, STARTUP and/or POWER OPERATION may proceed until performance of the next required CHANNEL FUNCTIONAL TEST provided the inoperable channel is placed in the tripped condition with I hour.

SALEM - UNIT 2 3/4 3-6 Amendment No.ll4

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T

_TAntE-4.3-1 "7

IRIP SYSif M INSTHilMlNI ATION SURVEILL ANCE HEQUIH1MINii REACiult

'j.

CIIANNFL MODES IN WillCll FUNCi10NAl

$tIRVLitiANCE

~4 CifANNEL m

Citt CK CAllBRATION TEST HiQ:llHl 0 f ilNCT IOftAI. UNil -

N.A.

5/U(9)

N.A.

1..

Manual iteactor Trip Switch 5

D(2),M(3)

M I, 2 2.

Power Range,ficutron flux and Q(6) 3.

Power Range, Neutron flux, R(6)

M 1, 2 N.A.

liigh Positive Rate M

1, 2 4.

Pew 2r Rrnge, fleutron flux, R(6)

N.A.

liigh Negalive Itate a.,

5.

Intermediate Itange, R(6)

S/U(1) 1, 2 and

5 i'

Neutron flux 6.

Source Range, Neutron flux S(7)

R(6)

M and S/U(1) 2, 3, 4, 5 a n.1

Z M

I, 2 5

R

'. Overtemperature of M

1, 2 5

R 11. Overpower ai g

M 1, 2 5

R m

9.

Pressurlier Pressure--low M

I, 2 5

R Po 10.

Pressurizer Pressure--Illyh Q

1, 2 5

R 2

11.

Pr essurizer Water Level-..iligt

{

M I

5 G

12.

luss of Flow - Single loop l

l

+

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ML20118A401

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