ML20095C917
| ML20095C917 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 08/16/1984 |
| From: | Bayne J POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK |
| To: | Varga S Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML093490893 | List: |
| References | |
| IPN-84-32, NUDOCS 8408230164 | |
| Download: ML20095C917 (7) | |
Text
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"~ o-August 16, 1984 IPN-84-32 Director of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C.
20555 Attention:
Mr. Steven A. Varga, Chief Operating Reactors Branch No. 1 Division of Licensing
Subject:
Indian Point 3 Nuclear Power Plant Docket No. 50-286 Appendix R Fire Protection Program
References:
(1)
Letter dated May 20, 1983, IPN-83-44, J. P.
Bayne to S. A Varga (2)
Letter dated July 22, 1983, S. A. Varga to J.P.
Bayne (3)
Letter dated September 26, 1983, IPN-83-80, J.P.
Bayne to S.
A. Varga (4)
Letter dated December 13, 1983, IPN-83-99, J. P.
Bayne to S.
A. Varga (5)
Letter dated February 2,
- 1984, D. G.
Eisenhut to J. P.
Bayne (6)
Letter dated June 15, 1984, IPN-84-18, J.P.
Bayne to S. A. Varga (7 )
Letter dated August 13, 1984, I P N-8 4 - 29,
J. P.
Bayne to S. A. Varga
Dear Sir:
By letter dated September 26, 1983 (Reference 3) the Authority informed the NRC of the establishment of an Appendix R Task Force and the initiation of a comprehensive review and re-evaluation of Indian Point 3 compliance with 10 CPR 50,.
Appendix R, Sections III.G, III.J, III.O and III.L.
The scope of the Authority's activities included, but was not limited to, the specific areas of concern identified in the draft Safety f
Evaluation Report enclosed with Reference 2.
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8408230164 840816 PDR ADOCK 05000286 i
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. This letter and its attachments summarize the results of the Authority's re-evaluation of Indian Point 3 compliance with Sections III.G and III.L of Appendix R.
Issues related to compliance with Section III.O requirements have been addressed in Reference 7.
With respect to Section III.J, it should be noted that implementation of modifications to achieve III.G or III.L compliance might necessitate modification of the emergency lighting system.
Thus full compliance with Section III.J can only be attained subsequent to completion of design changes required for compliance with Section III.G, or Section III.L, or both.
The attached report describes in detail existing and proposed capabilities which provide or will provide an equivalent level of fire protection to that dictated by verbatim compliance with Section III.G.
Included in the report (Section 6) are four requests for exemption from the literal requirements of the regulation.
Modifications necessary to support the aforementioned exemption requests or to achieve full compliance in specified plant locations are described in Section 5 of the report.
Implementation of the various modifications will require a significant engineering and design effort by the Authority and/or its contractors.
In order to coordinate implementation of the necessary modifications with scheduled plant outages, the Authority requests an exemption, pursuant to Sections 50.12, 50.48(c) and 50.48(d) of 10 CFR, to the schedular requirements of Section 50.48(c) and 50.48(d) to allow for final completion of all plant modifications prior to startup from the next (cycle 4/5) refueling outage.
As shown in, intermediate implementation dates have been developed for modifications which can either be performed during power operations or during the mid-cycle steam generator inspection outage, scheduled to begin in mid-October, 1984.
The design and implementation of these modifications are ongoing efforts.
Portions of these modifications are being/will be performed prior to the dates indicated in the schedule.
Intermediate implementation dates for items 17, 18 and 19 will be provided by September 11, 1984.
Should you or your staff have any questions regarding this matter, please contact Mr. P. Kokolakis of my staff.
Very truly yours, f
5 (1_da P ayne Exe ut ve Vice President Nucle r Generation cc:
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-,..u Sch dula for CompletOd Implemsntation of Appendix R Modifications Modification Schedule (1)
Provide local indication of main mid-cycle steam pressure in the vicinity of outage the atmospheric dump valves.
(2)
Provide local indication of N2 mid-cycle pressure (to the main steam outage atmospheric dump valves) and relocate a N2 bottle, with quick disconnects, to the dump valve area.
(3)
(a) Develop repair procedures and September 15, 1984 training to facilitate necessary post-fire actions (e.g. repair of RHR pump power cable).
(b) equipment (kits) available on site.
September 15, 1984
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(4)
Provide for local operation and control mid-cycle outage of the 480v switchgear breaker for the no. 33 motor driven auxiliary feedwater pump.
(5)
Install an area-wide automatic mid-cycle outage suppression system in the auxiliary feedwater pump room.
(6)
Review and upgrade, as necessary, review ongoing; all fire area boundaries and upgrade where required, internal barriers credited in the as permitted by analysis to ensure adequate fire operational restrictions rating.
(final implementation by cycle 4/5 refueling outage)
(7)
Inrtallation of radiant energy mid-cycle outage shields / wraps inside containment.
(8)
Provide a one hour-rated wrap mid-cycle around source range (N31) conduit from outage the electrical penetration (outside VC to a minimum of twenty feet into the upper electrical tunnel.
(9)
Provide a one hour-rated wrap / barrier mid-cycle around the trays containing required outage instrumentation in the electrical penetration area.
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M:dification Schedule L
(10)
Complete installation of an alternate cycle 4/5 shutdown diesel generator.
refueling outage (11)
Complete installation of a source cycle 4/5 range flux channel independent of the refueling outage l
cable-spreading room.
(12)
Provide isolation capability for cycle 4/5 wide-range RCS pressure instrumentation refueling outage l
at the electrical penetration area with l
local readouts at the AFW and charging control stations.
(13)
Provide isolation capability for cycle 4/5 wide-range RCS temperature instruments refueling outage at the electrical penetration area with local readouts at the AFW control station.
(14)
Provide a partial-height non-combustible October 31, 1984 barrier to protect CCW pump no. 33.
Wrap the power cable for CCW pump no. 33.
(15)
Reroute one channel each of wide mid-cycle outage range steam generator level (LT-447D) and pressurizer level (LT-462).
(16)
Relocate the three air operated cycle 4/5 valves in the steam supply line to refueling outage the auxiliary feedwater pump turbine (1310A, 1310B, and PCV 1139).
(17)
Modify the door between the cable tunnels and the cable spreading l
room so that the door closes on indication of a tunnel fire.
i (18)
Extension of automatic detection systems in various fire areas.
(19)
Modify as necessary the hatchway at the end of the upper electrical tunnel.
Intermediate implementation dates will be provided by September 11, 1984 but in all cases the modifications will be implemented by the end of the cycle 4/5 refueling outage.
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... -., to IPN 32 Reevaluation of Appendix R Section III'.G Requirements for-Indian Point Nuclear Power Plant Unit 3 New York Power Authority Indian Point Unit 3-
' Docket NO. 50-286
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