ML20078M668
| ML20078M668 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 10/19/1983 |
| From: | Hukill H GENERAL PUBLIC UTILITIES CORP. |
| To: | Stolz J Office of Nuclear Reactor Regulation |
| References | |
| 5211-83-293, NUDOCS 8310250261 | |
| Download: ML20078M668 (22) | |
Text
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Nuclear
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Route 441 South Middletown, Pe.;nsylvania 17057-0191 717 944 7621 TELEX 84 2386 Writer's Direct Dial Number:
October 19, 1983 5211-83-293 Office of Nuclear Reactor Regulation Attn:
John F. Stolz, Chief Operating Reactors Branch No. 4 U. S. Nuclear Regulatory Commission Washington, D.C.
20555
Dear Sir:
Three Mile Island Nuclear Station, Unit 1 (TMI-1)
Operating License No. DPR-50 Docket No. 50-289 Purge Valve Operability, NRC Safety Issue B-24 In response to your letter of July 8,1983, please find enclosed the additional information you requested, which do not require an amendment to the TMI-l Technical Specifications:
These Items are:
- 1) An analysis which demonstrates the protection of safety related equipment located down stream of the purge isolation valves from the environment created by escaping air and steam during a Loss of Coolant Accident (LOCA),
- 2) A discussion of the TMI-l plant specific configuration which l
negates the need to install debris screens up stream of the purge isolation valves, and
- 3) An analysis of the ECCS back pressure with the consideration that the purge / vent valves are open at the initiation of the LOCA.
Sections 1, 2 and 3 of the attachment address each of these Items respectively.
1 JE The items from your July 8,1983 letter which do require an amendment to
-n a.
the TMI-l Technical Specifications and therefore, a revision to Technical 08 Specification Change Request No.116, will be forwarded by a separate letter.
These items include:
O l
L
- 1) Adoption of iodine spiking Standard Technical Specifications, So vic
- 2) Specific reactor building purge isolation valve position limits E'
including limitations on when reactor building purging is per-g gg
- mitted, 0
ca n.n.
GPU Nuclear Corporation is a subsidiary of the General Public Utilities Corporation I
i
Mr. John F. Stolz 5211-83-293
- 3) Acceptance criteria for leakage-tests of reactor building purge isolation valves, and
- 4) Various' plant surveillance frequency adjustments, including those mandated as a result of limited access to the reactor building as a result of limited purge capability. Addition-ally Technical Specifications for purge valve closure time testing will not be provided since this requirement is already included in our Technica1' Specifications by the inclusion of the purge valves in the ASME Section XI valve testing program and Technical Specification 4.2.2.
This letter and its attachment, in conjuction with the revised Techncial Specification Change Request No. 116 which will be sent separately, should serve to close NRC safety issue B-24 for TMI-1.
Sincerely, F
Director, TMI-1 HDH:CJS:vjf Attachment cc:
J. Van Vliet R. Conte l
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ATTACHMENT TO GPU NUCLEAR LETTER No. 5211-83-293 REACTOR BUILDING PURGE ISOLATION VALVES i
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'5ECTION 1 An analysis.was performed (and is attached) which cercnstrates that the cownstream ductwork cf the reactor building purge exhaust anc supply systets L,
will withstand post _ LOCA conditions with purge valves 1.4miteo to 30o open.
- This analysis demonstrates that the duct work maintains its integrity and there will be no hostile environment for either safety related equipment or structures cownstream of tne purge valves.
Tne assuned 3.5 sec. closure time and resulting analysis is extremely conservative, since the air operatec purge valves close within approximately.5 seconds after receipt of closure signal and purge valve closure is also initiated on reacter trip.
(See attacned analysis.)
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Reactor Building Pressure, psig REACTOR BUILDING PRESSURE VERSUS TIME FOR THE DBA WITH CONTINUOUS STEAM RELEASE 2
WITH 3 REACTOR BUILDING AIR COOLERS THREE MII.E ISLAND NUCLEAR STATION UNIT I 44%et].v?z m
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Georis Screens The July 8,1983 NRC letter (Item 1.c) requestet ina GDUN..."shoulc provice an acceptable method of ensuring that the isciati:n valves in the purge and vent lines will not be prevented from closing c: prc:erly seating cy cebris.
An acceptable method is the installation of ce::is s:reens in these lines.
If debris screens are to be utilizec, they shoulc te seismic Category 1 cesign and installed about one-pipe diameter away from the inner sice of each inocarc isolation valve.
The piping between the debris screen anc the isolation valve shoulc also be oesigned to seistic Category I cesign."
GoUN has cetermined tnat both the Reactor Builcin; Ferge Supply anc Exhaust Isolation Valves will not be prevented from closing :: properly seating by decris.
It is understood from discussion with the NRC Staff ano the July 8, 1983 and
, April 30, 1982 letters that the design basis accioents fer wnien these valves are relied upon are:
- 1) Fuel Handling accident in Reactor Builcin; (negligable storec energy released to containment) potential for racicactive release to public; of interest because of ability to purge curing refueling operations) and;
- 2) Large Break LOCA (high stored energy release to containment, potential for radioactive release to puoli:; of interest because of ability to purge in limited manner during Operation).
Due to the negligable energy released to containnent from the Fuel Han ling accicent in the Reactor Builcing, there is virtcally no possitility of cebris being generated ano transported to the area of inese valves which could P0se an operability hazard to these isolation valves.
Small break LOCA is not considered to pose an opers:ility nazarc to the purge valves, again because of the minimal release of stcret energy into containment.
A more cetailed discussion is proviceo below fc tne supply anc exhaust valves for the large break LOCA.
Reactor Building Purge Supply Valve an: Duttwers AH-V-lC is mountec approximately 3 feet from tre ::ntainment wall in Seismic I ductwcrk.
The ductwork then turns to a vertical crientaticn anc encs at a penetration in the floor at an elevation of 308' (a;::cx. 25 feet).
Altncugn this ductwork was originally cesigneo to Seistic III, it will maintain its integrity througn an SSE and thereby, not become en creracility hazar: to the purge valve.
Tnere are no high energy reactor :::lar lines in prcximity tc the valve or cuttwcrk, so there is not jet it:ingement concern (i.e., One jet from the postulated RCS line break causing insulatior c ciner " light" material to become cebris).
SECT:0N 2 Debris Screens - continuec Additionally, all material in proximity to the cu:tw:rk outlet is f astenec in a substantial manner, thus eliminating the threat of :e ris rea:nin; tne valve.
As an additional measure acministrative ::ntrols will be in place te ensure that no foreign material is left in the proxirity of tne auctwork outlet.
Should any debris be generated during t9e LCCA, tne cebris woul: have to travel a tortuous path (i.e., out the "D" rin;, ar0unc the 346' elevation floor, cown the stairwells 2 floors, and around tne 251' elevation cf tne Reactor Building, without being caught on piping or cajor equipment enroute, in 3.5 seconos, in order to pose an operability nazard tc AH-VlC. Tnis neglects the fact that AH-VID is air operated an: cleses in approximately.5 seconds.
GPUN has determined that the current configuration of AH-VlC provides reasonable assurance that debris will not be an operability hazard to AH-VIC.
Reactor Buildino Purce Exhaust Valve AH-VlB is mounted adjacent to the Reactor Building wall in seismic 1 ouctwork with no inboard ductwork.
There are no high energy reacter coolant lines in' proximity to this valve, so there is not jet impingenent concern.
Tnere is no piping with insulation (which could become cebris) in close proximity to AH-VlB.
Additionally, all material in proximity to tnis valve is fastened in a substantial manner, thus eliminating the threat of cecoming cebris and aios in minimizing the potential for debris reaching the valve.
Should any cebris be generated during a large LOCA, the debris woulo have to travel a tortuous path around the various floors in the building and n:t be trappec on any equipment or piping enroute (within 3.5 seconos) in croer to become an operability hazard to AH-VlB.
This neglects the appr:ximate.5 secen: closure time of AH-VlA.
As an aoditional measure, acministrative controls will be implemented to ensure that no foreign material is left in close proximity to AH-VlB.
GDUN has determined that the current config. ration of AH-VIE provices reasonable assurance that debris will not be an c: era ility hazarc t: A.9-VlE.
Conclusion Based on the above no detris screens are neecec f0: tne TVI-l Purge Isciation i
valves.
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An analysis was perforred using the contecpt EI/26 ca pter code to deterne sat effect having the purge supply and etaust valves cpen at the onset of a IDCA would have on contain:ent pressure and therefere, ECCS backpressure.
The analysis was performed assu'ng;
-1) Purge valves initially open at 30,
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2
- 2) mst severe break size (8.55 ft double ended break at the ptrp discharge)
- 3) 4 psig Conr=4,mmt Building 1 solation Signal takes place in about.5 seconds, and 4)- Purge valves stay open for 4 seconds and close instantaneously.
'Ihe results 'of this anapsis are shown in Figure 1 sich shows that the purge valves being open at 30 for 4 seconds has a negligible effect on the cen-in-ment pressure response.
Fipre 2 shows the ccrpariscas on a @_ led scale, and the insignificant decrease in containment pressure due to the open valves 2.
can be observed.
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