ML20235D400

Advises That During Insp at Facility,Some of Installed post-accident Noble Gas Effluent Sys & Associated Tech Specs Found Contrary to Regulatory Positions.Technical Assistance Re Acceptability of Installations & Tech Specs Requested

ML20235D400
Person / Time
Site:	Callaway, 05000000
Issue date:	04/28/1986
From:	Hind J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:	Thompson H Office of Nuclear Reactor Regulation
Shared Package
ML16342B348	List: IA-87-121, Discusses Inservice Test Programs Re Full Stroke Exercising of Normally Closed Swing or Tilting Disk Check Valves Per 10CFR50.55a & Section XI of ASME Code ML20235B266 ML20235B268 ML20235B295 ML20235B304 ML20235B322 ML20235B406 ML20235B470 ML20235B514 ML20235B581 ML20235B613 ML20235B673 ML20235B768 ML20235B785 ML20235B799 ML20235B859 ML20235B877 ML20235B922 ML20235C007 ML20235C967 ML20235C970 ML20235D014 ML20235D041 ML20235D091 ML20235D157 ML20235D188 ML20235D233 ML20235D400 ML20235D433 ML20235D484 ML20235D532 ML20244B491 ML20244B568 ML20244B571 ML20244B913 ML20244B937 ML20244B941 ML20244B943 ML20244C126 ML20244C271 ML20244C361 ML20244C777 ML20244C785 ML20244C833 ML20244C935 ML20244C940 ML20244C986 ML20244D413 ML20244D552 ML20244D582 ... further results
References
FOIA-87-121 GL-83-37, NUDOCS 8707100155
Download: ML20235D400 (2)

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April 28,1986 MEMORANDUM FOR: H. L. Thompson, Jr., Director, Division of '

Pressurized Water Reactor Licensing-A, NRR FROM: Jack A. Hind, Director, Division of i Radiation Safety and Safeguards, Region III

SUBJECT:

REQUEST FOR TECHNICAL ASSISTANCE REGARDING POST-ACCIDENT NOBLE GAS EFFLUENT MONITORING SYSTEMS AT CALLAWAY ]

During a recent inspection of the Callaway County Nuclear Station, the f inspectors noted that some of the installed post-accident noble gas effluent 7 systems and the associated technical specifications appear contrary to  ;

regulatory positions. These items concern the technical adequaty of installed q radiation detectors to monitor the post-accident main steam safety relief a valves / power-operated relief valve (PORV) pathway and the apparent discrepancy between Callaway Technical Specifications 3.3.3.6 and 4.3.3.6 and regulatory  : '

positions stated in Generic Letter 83-37. Details regarding these items are '

attached.

We request that you provide us guidance concerning the acceptability of the The Re above licensee technical installations contacts and technical for this matter are Charlesspecifications.388-5261)gionIII Gill (FTS or '

L. Robert Greger (FTS 388-5644). i i

b

- Nack A. Hind,. Director 5 Division of Radiation Safety -

and Safeguards [.

Attachment:

As stated cc w/ attachment:

P. O'Connor, NRR R. Bellamy, RI e D. Collins, RII -

R. Hall, RIV -

F. Wenslawksi, RV C. Norelius, RIII _

Resident Inspector qgi. i ~

I J RIII,_Callaw g RIII s RI ((hay RI R(II I ,

YE GT11/as y i 04/28/86 N B707100155 870701 l-LIA -121 PDR

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l ATTACHMENT Fain Steam PORV_ Plume Radiation Monitors i

During the revie4 of the post-accident noble gas effluent monitoring s the main steam safety relief valves / power-operated relief valve (PORV)ystem pathway, for the inspectors nated that the technical adequacy of the licensee's installed radiation monitor!. was questionable. The radiation monitors are located on the auxiliary building roof and oriented, shielded, and co111 mated to detect the plume from the PORVs. If the PORVs are blocked, the radiation monitors appear incapable of responding to post-accident main steam release via the safety relief valves. The PORVs are not code safety valves and are presently not governed by the technical specifications; thus, the licensee may operate the plant with blocked PORVs without restriction. Also, in accident circumstances the licensee may elect to block leaky PORVs to prevent the release of radioactive effluents and/or the loss of secondary system coolant. The inspectors informed the licensee that the acceptable location for externally mounted monitors specified by NUREG-0737, Item II.F.1, Attachment 1 is on the main steam line upsteam of the safety valves and PORV and that NRR is presently evaluating a similar technical issue at the D. C. Cook Nuclear Power Plant (Inspection Reports Nc. 50-315/85011; 50-316/85011, Unresolved Items No. 315/85011-05; No. 316/85011-04).

Technical Specifications 3.3.3.6 and 4.3.3.6 During the review of the licensee's commitments to NUREG-0737, Item II.F.1, Attachment 1, the inspectors noted that the installed post-accident noble gas effluent radiation monitors were apparently those described in Appendix 7A and Subsection 18,2.12.2 of the FSAR. The post-accident noble gas effluent radiation monitors identified in the f5AR are used to monitor effluents from the plant unit vent, the radvaste building, the main steam PORVs, and steam discharge from the turbine-driven auxiliary feedwater pump. Generic Letter 83-37, "PWR NUREG-0737 Technical Specification," dated November 1, 1983, specifies that all of the licensee identified post-accident noble gas effluent radiation monitors should be included in the accident monitorino technical specifications; however, Callaway Technical Specifications 3.3.3.6, " Accident Monitoring Instrumentation Limiting Condition for Operation," and 4.3.3.6,

" Accident Monitoring Instrumentation Surveillance Requirements," include only the plant unit vent high range noble gas monitor.

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