ML19246C431

Amend 17 to License DPR-70,changing Tech Specs to Require Actuation of Safety Injection Based on two-out-of-three Channels of Low Pressurizer Pressure

ML19246C431
Person / Time
Site:	Salem
Issue date:	06/07/1979
From:	Schwencer A Office of Nuclear Reactor Regulation
To:
Shared Package
ML19246C432	List: ML19246C431
References
NUDOCS 7907240597
Download: ML19246C431 (12)

Text

yt,p>" "c,k ui UNITED STATES NUCLEAR REGULATORY COMMISSION y'

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WASHINGTON, D. C. 20555

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PUBLIC SERVICE ELECTRIC AND GAS COMPANY PHILADELPHIA ELECTRIC COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-272 SALEM NUCLEAR GENERATING STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.17 License No. DPR-70 1.

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

A.

The application for amendment by Public Service Electric and Gas Company, et al. (the licensee) dated May 7,1979, 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 activites authorized by this amendment can be conducted without endangeting the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.

The issuance of this amendment will not be inimical to the common defense and recurity 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.

y go@

426 043

. 2.

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

"(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.17, are hereby incorJorated in the license. The licensee shall operate the 'acility in accordance with the Technical Specifications."

3.

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

FOR THE NUC EAR REGULATORY COMMISSION

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D k t % d d 4 W 0 l-

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A. Schwencer, Chief Operating Reactors Branch #1 Division of Operating Reactors

Attachment:

Changes to the Technical Specifications Date of Issuance: June 7, 1979 426 044

ATTACHMENT TO LICENSE AMENDMENT NO.17 FACILITY OPERATING LICENSE NO. DPR-70 00CKET NO.

50-272 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change. The corresponding overleaf pages are also provided to maintain document completeness.

Pages 3/4 3-15 3/4 3-22 3/4 3-23 3/4 3-28 3/4 3-31 4

mV 426 045

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TABLE 3.3-3 (Continued) wp 9

ENGINEERED SAFETY FEATURE _ ACTUATION SYSTEM INSTRUMENTAT10fl M

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k U

HINIMUM TOTAL NO.

CilANNELS CllANNELS ApPLICABl.E MODES ACTION Q

FUNCTIONAL UNIT OF CilANNELS TO TRIP OPERABLE 1, 2, 3" f.

Steam Flow in Two Steam Lines-liigh Four Loops 2/ steam line 1/ steam line 1/ steam line 14 Operating any 2 steam lines w

D Three Loops 7/ operating YN/any 1/ operating 15 w

g Operating steam line operating steam line steam line COINCIDENT WITil EITilER 0

1, 2, 3 T

--L w-Low avg M

2T any 1T any Four Loops 1T3yg/ loop avg avg Operating loops 3 loops N#

1 T

in 1T in any 15 Three loops 1Tavg/

avg avg Operating operating any operating two operating loop loop loops

TABLE 3.3-3 (Continued)

TABLE NOTATION

1. rip function may be bypassed in this MODE below P-ll.

T Trip function may be bypassed in this MODE below P-12.

U The channel (s) associated with the protective functions derived from the out of service Reactor Coolant Loop shall be placed in the tripped mode.

The provisions of Specification 3.0.4 are not applicable.

ACTION STATEMENTS ACTION 13 - With the number of OPERABLE Channels one less than Number of Channels, be in HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />; however, one channel may be bypassed for up to I hour for surveillance testing per Specification 4.3.2.1.1.

ACTION 14 - With the number of OPERABLE Channel's one less tha Number of Channels, operation may proceed until performance of the next required CHANNEL FUNCTIONAL TEST, provided the inoperable channel is placed in the tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

ACTION 15 - With a channel associated with an operating loop inoperable, restore the incperable channel to OPERABLE status within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or be in HOT SHUTDOWN within the following 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />; however, one channel associated with an operating loop may be bypassed for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing per Specification 4.3.2.1.1.

ACTION 16 - With the number of OPERABLE Channels one less than Total Number of Channels, operation may proceed provided the inoperable channel is placed in the bypassed condition and the Minimum Channels OPERABLE requirement is demonstrated within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />; one additional channel may be bypassed for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing per Specification 4.3.2.1.1.

SALE" - UNIT 1 3/ 4 3-21 426 04F

TABLE 3.3-4 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS b FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUES 5*

1.

SAFETY INJECTION, TURBINE TRIP AND FEEDWATER ISOLATION a.

tianual Initiation Not Applicable Not Applicable b.

Autonatic Actuation Logic Not Applicable Not Applicable c.

Containment Pressure--High

< 4.7 psig

< 5.2 psig d.

Pressurizer Pressure--Low

> 1765 psig

> 1755 psig m

f e.

Differential Pressure

< 100 psi

< 112 psi j

between Steam Lines--High w

f.

Steam Flow in Two Steam Lines--

< A function defined as

< A function defined as

--Low-Low follows: A ap corresponding Tollows : A to corresponding High Coincident with T,yEow or Steam Line Pressure--

to 40% of full steam flow to 44% of full steam flow between 0% and 20% load between 0% and 20% load and and then a ap int.reasing then a Ap increasing linearly linearly to a Ap correspond-to a ap correscending to g

g ing to 110% of full steam 111.5% of full steam flow flow at full load at full load aa

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> 543*F T

> 541*F avg -

avg -

N os

> 480 p319 steam line

> 500 psig steam line pressure pressure c3 2.s

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-d-B ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS rg E

FUNCTIONAL UNIT TRIP SETP0lfiT ALLOWABLE VALUES G

2.

CONTAINMENT SPRAY a.

Manual Initiation Not' Applicable Not Applicable b.

Automatic Actuation Logic flot Applicable Not Applicable c.

Containment Pressure--liigh-fligh 1 23.5 psig i 24 psig 3.

CONTAINMENT ISOLATION R

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Phase "A" Isolation 1.

Manual Not Applicable Not Applicable 2.

From Safety Injection Not Applicable Not Applicable Automatic Actuation Logic b.

Phase "B" Isolation 1.

Manual Not Applicable Not Applicable 2.

Automatic Actuation Logic Not Applicable Not Applicable 3.

. Containment Pressure--liigh-liigh 1 23.5 psig 1 24 psig c.

Containment Ventilation Isolation 1.

Manual Not Applicable Not Applicable

TABLE 3.3-5 ENGINEERED SAFETY FEATURES RESPONSE TIMES INITIATING SIGNAL AND FUNCTION RESPONSE TIME IN SECONDS 1.

Manual Safety Injection (ECCS)

Not Applicable a.

Feedwater Isolation Not Applicable Reactor Trip (SI)

Not Applicable Containment Isolation-Phase "A" Not Applicable Containment Ventilation Isolation Not Applicable Auxiliary Feedwater Pumps Not Applicable Service Water System Not Applicable Containment Fan Cooler Not Applicable b.

Containment Spray Not Applicable Containnnt Isolation-Phase "B" Not Applicable Containment Ventilation Isolation

,Not applicable c.

Containment Isolation-Phase "A" Not Applicable Containment Ventilation Isolation Not Applicable d.

Steam Line Isolation Not Applicable 2.

Containment Pressure-Hich Safety Injection (ECCS) 1 27.0*

a.

b.

Reactor Trip (from SI) 1 3.0 c.

Feedwater Isolation 1 8.0 N

d.

Containment Isolation-Phase "A" 1 18.0 /28.O Containment Ventilation Isolation Not Applicable e.

f.

Auxiliary Feedwater Pumps Not Applicable N

g.

Service Water System 1 13.0 /48.0 SALEM - UNIT 1 3/4 3-27 At6 0:1

Oh TABLE 3.3-5 (Continued)

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ENGINEERED SAFETY FEATURES RESPONSE TIP.ES INITI ATING SIGNAL AND FUNCTION RESPONSE TIME IN SECONDS 3.

Pressurizer Pressure-Low a.

Safety Injection (ECCS) 1 27.0*/13.0f b.

Reactor Trip (from SI) 1 3.0 c.

Feedwater Isolation s 8.0 d.

Containment Isolation-Phase "A" 1 18.0f e.

Containment Ventilation Isolation Not Applicable f.

Auxiliary Feedwater Pumps Not Applicable g.

Service Water System 1 48.0*/13.0f 4.

Differential Pressure Between Steam Lines-High a.

Safety Injection (ECCS) 1 13.0f/23.0!f b.

Reactor Trip (from SI) 1 3.0 c.

Feedwater Isolation s 8.0 d.

Containment Isolation-Phase "A" 1 18.0f/28.0i!

e.

Containment Ventilation Isolation Not Applicable f.

Auxiliary Feecwater Pumps Not Applicable g.

Service Water System i 13.05/48.0##

5.

Steam Flow in Two Steam Lines - High Coincident with T

--LU*-'0" avg a.

Safety Injection (ECCS) 1 15.0#/25.0!#

b.

Reactor Trip (from SI) 1 S.0 c.

Feedwater Isolation 1 10.0 d.

Containment Isolation-Phase "A" 1 20.0#/30.0!#

e.

Containment Ventilation Isolation Not Applicable f.

Auxiliary Feedwater Pumps Not Applicable 9

Service Water System i 15.0#/50.0!#

h.

Steam Line Isolation 1 10.0 SALEM - UNIT 1 3/4 3-28 Amendment No. 17

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