ML19294B521

Forwards Info Re Implementation of TMI-2 Lessons Learned Task Force short-term Requirements

ML19294B521
Person / Time
Site:	Arkansas Nuclear
Issue date:	02/29/1980
From:	Trimble D ARKANSAS POWER & LIGHT CO.
To:	Eisenhut D Office of Nuclear Reactor Regulation
References
RTR-NUREG-0578, RTR-NUREG-578 1-020-27, 1-20-27, NUDOCS 8003040477
Download: ML19294B521 (2)

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. f- s i k EU h ARKANSAS POWER & LIGHT COMPANY PO5T C::;CE BOX 551 UTTLE ROCK ARKANSAS 72203 (501) 371 XJOO February 29, 1980 1-020-27 2-020-18 Director of !;uclear Reactor Pegulation ATTN: Mr. Darrell G. Eisenhut, Acting Director Operatir.g Reactors U. S. Nuclear Reculatory Comenission Washington, D. C. 20555

Subject:

Arkansas Nuclear One - Units 1 & 2 Docket Nos. 50-313 and 50-368 License Nos. DPR-51 and NPF-6 Implementation of Short Term Lessons Learned Requirements (File: 1510.3, 2-1510.3)

Gentlemen:

In response to questions received by telephone from your Mr. Charles Long concerning our implementation of short term Lessons Learned (NUREG-0578) requirements, the attached information is provided.

'!ery truly yours, Jcxm' w.0/ g David C. Trimble Manager, Licensing DCT:skm Attachment 80030dp VEVPE A Y OCLE '

P'TH UT:UT:EG SY STE *,'

Y77

f ITEM 2.1.1 PRESSURIZER HEATERS - ANO-1 I

An actual system heat loss measurement conducted in November of 1975, indicates that 82.75 KW of pressurizer heaters is sufficient to meet the capacity requirements of Item 2.1.1. Each diescl generator cus currently supplies 8A KW of proportional heaters and, therefore, the Item 2.1.1 power supply and beater redundancy requirements are met.

Because B&W made a generic recommendation that 125 KW be considered as the necessary pressurizer heater capacity, AP&L provided 42 KW of supplemental heaters powered from a swing bus that can be connected to either diesel generator.

Additionally, at least 42 KW of supplemental heaters, which normally receive power from non engineered safeguards buses, could be powered from either of the diesel generators. The method of supplying diesel generator power to these heaters is currently addressed in plant pro-cedurer.

ITEM 2.1.6.b DESIGN REVIEW OF PLANT SHIELDING An in-house review is being conducted to determine what corrective actions will be needed in this area in the long term. Necessary cor-rective actions will be identified by March 31, 1980, and will be provided tc you at that time.

We are reviewing the effects of radiation on safety equipment and will address this subject in the March 31 submittal.

ITEM 2.1.8.a. IMPROVED POST-ACCIDENT SAMPLING As statec in our letter to you of January 31, 1980, portable shielding is being purchased which can be used in emergency situations to reduce personnel exposure. Aside from this, our actions in the short term will be procedural in nature. A review of the sampling problems encountered at TMI-2 was conducted. Information gained from this review which can improve our emergency sampling capabilities is presently being drafted into plant procedures. The revised procedures will be implemented as soon as possible, but no later than March 31, 19e'.;

AN0's counting facility is now located in the turoine building and, therefore, it offers an envircament for sample analysis in which ra-diation and airborne contamination problems are minimized. In an emergency, chemical sampling for boron can also be accomplished in the turbine building.

ITEM 2.1.8.b INCREASED RANGE OF RADIATION MONITORS Each unit at AND has three monitors that can be used to quantify noble gases that may enter the secondary system in the event of a steam gene-rator tube leak. Noble gases in the secondary will first pass through the condenser air ejector monitors as described in the Unit FSAR's. The gas then passes into the plant vents upstream of the recently installed monitors described under Item 2.1.8.b of our January 18, 1980, lessons Learned implementation letter, and upstream of the original stack moni-tors described in the Unit FSAR's. Noble gases escaping out of relief or dump valves can be quantified by means of a calculation combining noble gas concentration (obtained from the monitors) and estimated flow out of the relief or dump valve.