ML20127P835

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Forwards Revised Installation Schedule & Justification for Implementation of Five Items Re post-accident Instrumentation in Suppl 1 to NUREG-0737,per Reg Guide 1.97 as Discussed in 850129 Meeting
ML20127P835
Person / Time
Site: FitzPatrick Constellation icon.png
Issue date: 06/28/1985
From: Brons J
POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
To: Vassallo D
Office of Nuclear Reactor Regulation
References
RTR-NUREG-0737, RTR-NUREG-737, RTR-REGGD-01.097, RTR-REGGD-1.097 JPN-85-53, NUDOCS 8507020528
Download: ML20127P835 (7)


Text

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@f Authonty Jmm 28,1985 JPN-85-53 Director of Nuclear Reactor Regulation U.S.

Nuclear Regulatory Commission Washington, D.C.

20555 Attention:

Mr. Domenic B. Vassallo, Chief Operating Reactors Branch No. 2 Division of Licensing

Subject:

James A.

FitzPatrick Nuclear Power Plant Docket No. 50-333 Regulatory Guide 1.97 Post-Accident Instrumentation Modifications

References:

1.

NYPA letter, C. A. McNeill, Jr. to D.

B. Vassallo, dated November 30, 1984 (JPN-84-77) regarding Regulatory Guide 1.97, Revision 2, Implementation Report.

2.

NRC letter D.

B. Vassallo to C.

A. McNeill, Jr.,

dated February 27, 1985 regarding Implementation of Regulatory Guide 1.97, Rev.

2.

Dear Sir:

The Authority's Implementation Plan for Regulatory Guide 1.97 (Reference 1) included a proposed installation schedule for the FitzPatrick plant.

On January 29, 1985, Authority representa-tives met with the NRC staff to discuss our implementation of the five items in Supplement No. 1 to NUREG-0737.

Subsequently, the NRC requested that the Authority further justify our proposed implementation schedule (Reference 2).

This letter responds to that request.

Attachment No. 1 is a revised implementation schedule for each of the Regulatory Guide 1.97 variables.

This supersedes the schedule included with Reference No.

1.

One new variable (Item No. 18) that was omitted from the prior schedule has been added.

Installation schedules for two variables (Items 22 and 23) have been shortened by one fuel cycle.

Four variables (Items 1, 10, 19, and 22) have extended installation schedules.

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s Attachment No. 2 justifies the revised implementation schedule.

For each Regulatory Guide 1.97 variable, estimates of engineering and design time, procurement and lead times are included.

In general, the engineering and design for each variable will require 10 to 12 months.

This time includes the preparation of procurement documents and the revision of plant drawings.

Because some of the equipment has very long lead times, procurement may require as long as 8 months.

Attachment No. 1 is both a realistic and best schedule for other reasons not described in the justification (Attachment No. 2).

At the January 29th meeting, the Autho ity described the modifi-cations scheduled for installation in upcoming refueling outages.

We are currently working on FitzPatrick plant modifications and improvements with an estimated value in excess of $160,000,000.

A list of some of these modifications and further justification as to why additional improvements cannot be made to this schedule is included with our "ATWS Rule" (10 CFR 50.62) schedule, transmitted under separate cover.

While none of the planned modifications are of such scope or size as to preclude the completion of other modifications, the number which can be safely and effectively implemented at one time is limited.

Physical limitations, such as on-site manpower, as well as fiscal, engineering and procurement limitations can significantly affect schedule.

In some cases, installation sequences can be changed to improve schedules, reduce the amount of duplicate work or to take advantage of developing situations.

Schedule flexibility allows the Authority to both operate FitzPatrick and complete modifications in an efficient, safe and cost-effective manner.

If you have any questions or would like to discuss this further, please contact Mr. J. A. Gray, Jr. of my staff.

Very truly yours o$'nC. Brons Senior Vice President Nuclear Generation J

cc:

Office of the Resident Inspector U.S. Nuclear Regulatory Commission P.O. Box 136 Lycoming, N.Y.

13093 i

Attachnent No. 1 to JPN 53 Page 1 of 3 SCHEDULE FOR INSTALLATION OF REGULATORY GUIDE 1.97 VARIABLES AT JAMES A. FITZPATRICK NUCLEAR POWER PLANT REGULATORY GUIDE 1.97. REV. 2 INSTALLATION COMPLETION ITEM MEASURED VARIABLE TYPE CAT.

DATE (Note 3) 1.

Coolant Level in A, B 1

Reload 8/ Cycle 9 Reactor Vessel 2.

Suppression Pool A.

D 1,2 Reload 7/ Cycle 8 Water Temperature 3.

Drywell Atmosphere A, D 1,2 Reload 7/ Cycle 8 Temperature 4.

Suppression Chamber A

1 Reload 7/ Cycle 8 Pressure 5.

Containment and A,

C 1

Reload 6/ Cycle 7 Drywell Hydrogen Concentration 6.

Containment and A.

C 1

Reload 6/ Cycle 7 Drywell Oxygen Concentration (for inerted containment plants).

7.

Neutron Flux (Note 1)

B 1

Reload 8/ Cycle 9 8.

Primary Containment B

1 Reload 8/ Cycle 9 Isolation Valve Position (excluding check valves) 9.

Radioactivity C

1 Reload 7/ Cycle 8 Concentration or Radiation Level in Circulating Primary Coolant (Note 2)

6 Attachment No. 1 to JPN-85-53 Page 2 of 3 SCHEDULE FOR INSTALLATION OF REGULATORY GUIDE 1.97 VARIABLES AT JAMES A. FITZPATRICK NUCLEAR POWER PLANT REGULATORY GUIDE 1.97. REV. 2 INSTALLATION COMPLETION ITEM MEASURED VARIABLE TYPE CAT.

DATE (Note 3) 10.

Containment Effluent 2 C

3 Reload 7/ Cycle 8 Radioactivity-Noble Gases (from identified release points including Standby Gas Treatment System Vent) 11.

Suppression Chamber D

2 Reload 8/ Cycle 9 Spray Flow 12.

Main Steamline D

2 Reload 7/ Cycle 8 Isolation Valves' Leakage Control System Pressure-13.

Primary System Safety D

2 Reload 6/ Cycle 7 Relief Valve Position, Including ADS or Flow Through or Pressure in Valve Lines 14.

Standby Liquid Control D

2 Schedule determined System Flow by ATWS Ruling.

15.

Standby Liquid Control D

2 Schedule determined System Storage Tank Level by ATWS Ruling.

16.

RHR Heat Exchanger D

2 Reload 7/ Cycle 8 Outlet Temperature 17.

Cooling Water D

2 Reload 8/ Cycle 9 Temperature to ESF System Components 18.

RHR Service Water D

2 Reload 7/ Cycle 8 System Temperature 19.

Cooling Water Flow D

2 Reload 8/ Cycle 9 to ESF System Components

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4 Attech2cnt No.1 to JPN-8563 Pago 3 of 3 SCHEDULE FOR INSTALLATION OF REGULATORY GUIDE 1.97 VARIABLES AT JAMES A. FITZPATRICK NUCLEAR POWER PLANT REGULATORY GUIDE 1.97. REV. 2 INSTALLATION COMPLETION ITEM MEASURED VARIABLE TYPE CAT.

DATE (Note 3) 20.

High Radioactivity D

3 Reload 8/ Cycle 9 Liquid Tank Level (Note 1) 21.

Emergency Ventilation D

2 Reload 8/ Cycle 9 Damper Position 22.

Vent Flow Rate E

2 Reload 8/ Cycle 9 23.

Status of Standby D

2 Reload 7/ Cycle 8 Power & Other Energy Sources Important to Safety (Note 2) 24.

Primary Coolant and E

3 Reload 8/ Cycle 9 Sump Accident Sample NOTES:

1.

The implementation schedule for this variable only includes installation of the ability to display it in the Control Room via the SPDS/ EPIC.

This will be completed in accordance with SPDS/ EPIC schedules.

If additional modifications are necessary, they will be completed during " Reload 8/ Cycle 9".

This additional time is required for equipment procurement.

2.

The implementation schedule for this variable only includes installation of the ability to display it in the control Room via the SPDS/ EPIC.

This will be completed in accordance with SPDS/ EPIC schedules.

3.

For the purposes of this schedule, " Reload 6/ Cycle 7" shall be interpreted to mean:

"30 days after the end of the 1985 Refueling Outage (Reload 6/ Cycle 7) or December 31, 1985, whichever is later."

" Reload 7/ Cycle 8" shall mean:

"30 days after the end of the 1986 Refueling Outage (Reload 7/ Cycle 8) or January 31, 1987, whichever is later."

" Reload 8/ Cycle 9" shall mean:

"30 days after the end of the 1987 Refueling Outage (Reload 8/ Cycle 9) or April 1,

1988, whichever is later."

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Attachment No. 2 to JPN-85-53 Page 1 of 2 JUSTIFICATION FOR SCHEDULED INSTALLATION COMPLETION DATES FOR R.G.

1.97 VARIABLES AT JAFNPP ITEM JUSTIFICATION 1.

12 months engineering / design required, including preparation of procurement documents and plant drawing revisions.

Procurement is estimated to take 8 months.

Lead times for Class IE trans-mitters and recorders is 26-30 weeks.

Possibility exists that a new electrical penetration will have to be installed.

This modification will be combined with the Reactor Vessel Water Level Instrumentation Modification (Generic Letter No. 84-23)

Implementation of this modification is currently under study.

Results of this study are expected by August 30, 1985.

Both modifications are scheduled for completion during the Reload 8/

Cycle 9 outage.

2.

10 months engineering / design required, including preparation of procurement documents and plant drawing revisions.

Engineering and design review is required.

Procurement is estimated to take 8 months.

Lead times for Class IE equipment is 26-30 weeks.

3.

Same as Item 2.

4.

Same as Item 2.

7.

See footnote 1, page 3, of the schedule for installation.

8.

12 months engineering / design required, including preparation of procurement documents and plant drawings revisions.

Procurement is estimated to take 13 months.

Lead times for Class IE solenoid valves with position limit switches is 52-56 weets.

9.

This parameter will be provided by the SPDS/ EPIC system which is scheduled for installation during the Reload 7/ Cycle 8 outage.

See also footnote 2, page 3, of the schedule for installation.

10.

Same as Item 9.

11.

12 months engineering / design required, including preparation of procurement documents and plant drawing revisions.

Procurement is estimated to take 8 months.

Lead times for Class IE i

equipment is 26-30 weeks.

Due to the heavy workload planned for

]

the Reload 7/ Cycle 8 outage, this modification has been scheduled for the Reload 8/ Cycle 9 outage.

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Attachment No. 2 to JPN-85-53 Page 2 of 2 JUSTIFICATION FOR SCHEDULED INSTALLATION COMPLETION DATES FOR R.G.

1.97 VARIABLES AT JAFNPP ITEM JUSTIFICATION j

12.

Same as Item 2.

13 Not applicable.

14.

In order to comply with the ATWS requirements, modification to the SLCS system are necessary since these modifications involve increase flow and/or storage of boron solution, the measure 1

parameters will be incorporated in the design.

15.

In order to comply with the ATWS requirements, modification to the SLCS system are necessary since these modifications involve increase flow and/or storage of boron solution, the measure parameters will be incorporated in the design.

16.

Same as Item 2.

i 17.

Same as Item 11, with the exception that procurement is estimated to take 4 months, with lead times of 8-10 weeks.

I 18.

Same as Item 2, with the exception that procurement is estimated to take 4 months, with lead times of 8-10 weeks.

19.

Same as Item 11.

20 Same as Item 7.

21.

Same as Item 2.

22.

Same as Item 11.

23.

Same as Item 9.

24.

Same as Item 11.

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