ML19332F235

Forwards Quarterly Rept of Safety Evaluations for Seabrook Station Unit 1 for Jul-Sept 1989.Temporary Mod Made to Main Control Board Fire Alarm Module & Procedure Developed for Charging Pump Operations W/Alternate Min Flow Protection

ML19332F235
Person / Time
Site:	Seabrook
Issue date:	11/30/1989
From:	Feigenbaum T PUBLIC SERVICE CO. OF NEW HAMPSHIRE
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NYN-89157, NUDOCS 8912140111
Download: ML19332F235 (5)

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N: JNew Hampshi're Ted C.feigenbaum ,

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Senior Vice Presidnnt and Chief Operating Officer NYN-89157 November 30, 1989 United States Nuclear Regulatory Commission Washington .

DC- 20555)

, Attention: Document Control: Desk References a) Facility Operating Licer)se NPF-67. Docket No. 50-443 b') PSNH Letter (SBN- [11) dated October 9,_1986, '10CFR50.59 ,j Evaluation," G. S.: Thomas to V. S. Noonan _j l

Subjects 10CFR50.59 Quarterly Report _.

-Gentlemen:

l Enclosed please find the Quarterly Report of 10CFR50.59 Safety Evaluations for.Seabrook Station. This report. covers the period of July 1,=1989, to September 31,. 1989', and is being submitted pursuant to the reporting requirements outlined in Reference (b).

Should you require further information regarding this matter, please contact Mr. Richard R. Belanger at (603) 474-9521, extension 4048.

Very truly yours, :I pC/de[ ~l Ted C. Feigenbaum _l

Enclosures:

cc a' Mr. William T. Russell Regional Administrator United States Nuclear Regulatory Commission i Region I'

_ , , '475 Allendale Road l

, b' King of Prussia PA 19406 ,

n Mr. Victor Nerses Project Manager

- *[ Project Directorate I-3

n. United States Nuclear Regulatory Commission w Division of Reactor Projects bo Washington, DC 20555

!* Mr. Antone C. Cerne 8 NRC Senior Resident Inspector  ! l 194 P.O. Box 1149 wm Seabrook. NH 03874 k Mg New Hampshire Yankee Division of Public Service Company of New Hampshire P.O. Box 300

• Seabrook, NH 03874 = Telephone (603) 474 9521

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,, ". November 30, 1989'

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t ENCLOSURE 1 TO NYN-89157 Seebrook Station l

' 10CFR50.59 Safety Evaluation Quarterly Report i , July 1, 1989 to September 31, 1989 ft

1. Desian Channes The below listed design change was made at Seabrook Station and a safety evaluation was performed pursuant to the requirements of 10CFR50.59. -

Design Coordination Report Number 86-330

Title:

Refueling Cavity Narrow Range Level Transmittor

Description:

This design change was implemented to add a new non-safety related l

narrow range water level indication system for.the Refueling Cavity. This instrumentation provides accurate high and low level alarms on the Main Control Board computer displays during refueling operations. This instrumentation has no control function and is-only used.during refueling operations.

Conclusion:

A 10CFR50.59 safety evaluation was performed for this design change and;1t was determined that this change will not create an unreviewed safety question. Changes to the Final Safety Analysis Report will be incorporated by means of a future amendment.

2. Minor Modifications The below listed minor modifications were made at Seabrook Station and safety

-evaluations were performed pursuant to the requirements of 10CFR50.59.

Minor Modification -Number 89-530

Title:

Relief Valve SI-V175 Deletion

Description:

This minor modification was implemented to delete relief valve SI-V175 and install a blind flange in its place. The relief valve originally provided thermal over pressure protection for the Boron Injection Tank (BIT) and its associated piping which was heat

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traced. The BIT and associated piping have been deleted but SI-V175 was left in the system to_ serve as a thermal relief. A review of the current system indicates that there is no heat source remaining upstream of the containment isolation valves which would necessitate thermal relief protection.

Conclusion:

A 10CFR50.59 safety evaluation was performed for this minor modification and it was determined that this change will not create an unreviewed safety question. Changes to the Final Safety Analysis Report will be incorporated by means of a future amendment.

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Minor Modifications- Number 89-549

Title:

' Diesel Generator Loading Calculation Correction

Description:

Due to a class lE/Non class 1E interface in a control circuit, a j Computer Room Air Conditioning Unit and a Drycooler were changed.-  ;

from the 120 second step to the 12 second step for the Diesel  !

M Generator 1A loading. The timing change was not reflected in the  ;

Diesel Generator Loading, Voltage Regulation and DG Fuel Oil -j p . Storage Tank minimum volume calculations. This minor modification implements-the necessary changes to the affected calculations to reflect these loading changes. This is a paperwork change and {

there are no hardware changes required.

Conclusion -A 10CFR50.59 safety evaluation was performed for this minor modification and it was determined.that this change will not create an unreviewed safety question. Changes to the Final Safety Analysis Report will be incorporated by means of a future amendment.

3. Temporary Modifications l

The below listed temporary modification was made at Seabrook Station.and'a safety evaluation was performed pursuant to the requirements of 10CFR50.59.  !

' Temporary Modification: Number 89-036

Title:

Temporary Puver for MCB Fire Alarm Module

Description:

This temporary modification involves the use of a temporary 120V AC power source for the fire alarm console on the Main Control' Board l i- (MCB) while maintenance is performed on UPS ED-I-4. The normal )

l power source to the fire alarm console is from a 120V AC UNINTERRUPTIBLE pwer, bus. The temporary power will be supplied L through a local convenience outlet powered from a'non-emergency j 120V AC power panel. To compensate for the use of power that is i not UNINTERRUPTIBLE, a fire watch will be posted at the fire alarm l console.

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L The fire alarm module is a. monitoring device, with no automatic E controle. There will be no impact on class 1E power sources.  !

i Other fire protection equipment described in the Technical Requirements Manual, Section 12, will operate in their normal modes.

Conclusion:

A 10CFR50.59 safety evaluation was performed for this temporary-modification and it was determined that this change will not create an unreviewed safety question. i

4. Technical Reouirements Manual No changes were made to the Technical Requirements Manual during this reporting period.

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5. ~ Final Safety Analysis Reoort The below listed final safety analysis report change request was issued and ,

a safety evaluation was performed pursuant to the requirements of '

10CFR50.59.

' Final Safety Analysis Report: Number FCR 89-061

Title:

FSAR Changes to Section 6.2.6 ,

Description:

This Final Safety Analysis Report (FSAR) change request was.

initiated to allow the use of an additional data analysis technique for the performance of the Integrated Leak Rate Test (ILRT). Currently the FSAR only describes the use of i the absolute method using mass data point analysis techniques. This change allows the use of the total time method endorsed in Section III.A.3(a) of 10CFR50 Appendix J.

This change request also changes the scheduling requirements to reflect 10CFR50 Appendix J, and corrects the ILRT design leakage rate table and the listing of systems vented to atmosphere during the ILRT.

Conclusion:

A 10CFR50.59 safety evaluation was performed for this final safety analysis and it was determined that this change will not create an unreviewed safety question.

6. Procedures The below listed procedure was approved and a safety evaluation was performed pursuant to the requirements of 10CFR50.59.

Procedures Number OS 89-1-18

Title:

Charging Pump Operations with Alternate Minimum Flow Protection

Description:

This procedure was developed for onetime use when the normal charging pump minimum flow path was disabled to support maintenance-on the flow orifice downstream of the minimum flow isolation valves. The procedure established-an alternate charging flow path which replaced the minimum recirculation flow path for the centrifugal charging pumps. The alternate path provided flow greater than or equal to the normal minimum flow recirculation line and the flow was directed to the Reactor Coolant System (RCS) rather than to the charging pump suction.

The procedure was utilized while the plant was in MODE 5, with Low Temperature Over Pressure Protection (LTOP) established. The flow path established in this procedure involved only safety class 1 and 2 piping with proper design characteristics for this service.

Conclusion:

A 10CFR50.59 safety evaluation was performed for this procedure and it was determined that this change will not create an unreviewed safety question.

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7.- Procedure Channes Procedure changes that require review and approval by-the Station Operation Review Committee (SORC) are subject to the-requirements of 10CFR50.59. No ;i procedure changes have been made during this reporting period that would require a change to the Final Safety Analysis Report.

8. Test or Exoeriments There were no tests or experiments performed during this reporting period-  ;

that require evaluations in accordance with 10CFR50.59. '

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