ML18081A517

From kanterella
Jump to navigation Jump to search
Provides Evaluation Results & Schedule for Implementation of Required Changes Re NRC Requirements for Auxiliary Feedwater Sys,As Discussed in NRC
ML18081A517
Person / Time
Site: Salem PSEG icon.png
Issue date: 11/01/1979
From: Librizzi F
Public Service Enterprise Group
To: Eisenhut D
Office of Nuclear Reactor Regulation
References
NUDOCS 7911090478
Download: ML18081A517 (5)


Text

PS~G Public Service Electric and Gas Company 80 Park Place Newark, N.J. 07101 Phone 201 /430-7000 November 1, 1979 Director of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C.

20555 Attention:

Mr. Darrell G. Eisenhut, Acting Director Division of Operating Reactors Off ice of Nuclear Reactor Regulations Gentlemen:

NRC REQUIREMENTS AUXILIARY FEEDWATER SYSTEMS SALEM GENERATING STATION UNIT NO. 1 DOCKET NO. 50-272 We have reviewed NRC letter,.NRC Requirements fo_r Auxiliary Feed-water Systems at Salem Unit 1, dated September 21, 1979, and its enclosures.

The design and procedures of Salem No. 1 were evalu-ated against the requirements in Enclosure 1.

The results of this evaluation and an associated schedule for implementation of required changes is as follows:

1.

Section X.12.3.1.1, GS-2 The following valves have been administratively locked open:

lAFl, ll-13AF3, ll-14AF20, ll-14AF22, ll-14AF10, and ll-14AF86.

Surveillance Procedure SP{O) 4.7.l.2(a) is being revised to change the normal position of these valves from open to locked open.

This procedure is completed once each 31 days in accordance with Technical Specification 4.7.1.2.

The revision to this procedure will be completed by November 1, 1979.

2.

Section X.12.3.1.2, GS-3 Th~ NRC staff is currently reviewing a proposed change to the Technical Specifications that would remove the requirement of reducing auxiliary feedwater flow when steam generator level is less than 10%.

If this change is approved and the Technical Specifications are amended, appropriate procedural changes will be initiated at that time.

l!IO:l*lffi'.S r:1Qj)

A oo/

5

///.)

llrnlSOI' SEll\\'ICE f

'1911090 Lf1-r 95-2001 l200M) 2-78

Dir. of NRR 2 -

11-1-79

3.

Section X.12.3.1.3, GS-4 Operating Instruction III-10.3.1 provides the detailed steps required to transfer the AFP suction. to an al-ternate *source.

The AFT has low and low-low level alarms.

The alarm response for both of these alarms directs the operator to align the suction to an alternate suction in accordance with OI III-10.3.1.

In addition, Technical Specification 3.7.1.3 requires the alignment of the AFP suction to an al terna.te source within four hOurs should the AFT become inoperable.

Ad-ditional procedural steps will be added to the appro~

priate Emergency Instructions to caution the operator to monitor the AFW supply water in use.

The sequence of OI III-10.3.1 will lead the operator to use the alter-nate sources of water in the proper' sequence.

The changes to the Emergency Instructions will be completed by December 1, 1979.

4.

Section X.12.3.1.4, GS-6 Existing station administrative and surveillance pro-cedure~ contain adeq~ate ~ontrols and the appropriate steps required to return a system to an operable con-dition following maintenance or surveillance testing~

Therefore, it 1.s not deemed necessary to revise sta-tion procedures to require a second valve verification.

During plant heatup and startup and during operations in hot standby, the Auxiliary Feedwater System is*used to maintain steam generator level.

This satisfies the requirement for performing a flow test.

In addition, Technical Specification 3.7.1.2 requires that the Auxiliary Feedwater System be in its proper valve line-up prior to entering Mode 3 operation.

5.

Section X.12.3.1.5, GS-7 The Auxiliary Feedwater System has been designed as a class IE safety grade system.

The Auxiliary Feedwater System has been designed to include features as itemiz~d below:

..... *--/:-

Dir. of NRR 3 -

1.

Automatic initiation by the following detection signals will start the motor driven pumps; loss of offsite power, loss of main feedwater, low-low level in one steam generator and safeguards sequence signal.

Auto~atic start for the turbine driven pump is from loss of offsite power, low-low level in two steam generators and a 4 KV bus under voltage protection system signal.

2.

The automatic initiation signals and circuits are designed-~e prevent system malfunction for a signal failure.

11-1-79

3.

The system initiation signals and circuits are designed for complete testing.

4.

Power supply for the system circuits and initiation signals are from the unit vital buses.

5.

Manual initiation of the system may be accomplished from either the Control Room or locally at the pumps.

The circuits for manual initiation are designed for single,failure.

6.

The motor driven auxiliary feedwater pumps are included as a part of the sequential loading for the emergency diesel garierators.

7.

The failure of the automatic initiation signals and circuits will not effect the capability for manual initiation of the system:.

6.

Section X.12.3.2.1 The Auxiliary Feedwater -Storage. Tank has both a low and a low-low level alarm for Control Room annunciation and indi-cation.

The low level alarm allows approximately 30 minutes for operator action and the* low-low level 10 minutes.

Dir. of NRR 4 -

11-1-79

7.

Section X.12.3.2.2 A review of station logs and records is being conducted to determine if the Auxiliary Feed Pumps have been run in such a manner as to satisfy the requirements of this recommenda-tion.

If this cannot be documented, a special test pro-cedure will be* developed for each pump not previously tested.

This procedure would be completed at the earliest appropriate time, without impacting on station operation.

The require-ments of this recommendation will be completed by January 1, 1980.

8.

Section X.12.3.2.3 Safety grade indication of auxiliary feedwater flow to each steam generator is provided in the Control Room.

The indi-cating channels are designed to the same criteria as the pro-tection system indicators.

9.

Section X.12.3;2.4 Since we have three (3) Auxiliary Feed Pumps and the surveil-lance *procedures only allow tes.ting of one pump at a time, we maintain the capability to del.iver at least 100% of the required auxiliary feedwater flow at all times.

Therefore, this recom-mendation is not applicable.*

10.

Section X.12.3.3.1,.GL-2 We are going to modify the make-up supply valve (1DR6) to the auxiliary feedwater storage tank to provide for automatic open-ing upon low pump suction pressure.*

This plant modification will be completed during the *next refueling outage (scheduled fo~ Fall 1980)..

11.

Section X.12.3;3.2, GL-5 The auxiliary feedwater system has beeri designed as a Class lE safety. grade system.

Enclosure *2 "Basis for Auxiliary Feedwater Flow.Requirements"* has been referred to the Westinghouse* Electric Corporation for evalu-ation.

All efforts will be made to expedite these analyses.

Dir. of NRR 5 -

11-1-79 If you should have any questions, please do not hesitate to contact us.

Very truly yours,

-f.f~:F?

Frank P. Librizzi General Manager -

Electric Production