ML19207B509

Responds to NRC 790531 Ltr Re Violations Noted in IE Insp Rept 50-302/79-13.Corrective Actions:Personnel Have Been Cautioned That Variance from Approved Procedures Must Be Implemented by Approved Procedural Controls

ML19207B509
Person / Time
Site:	Crystal River
Issue date:	06/22/1979
From:	Stewart W FLORIDA POWER CORP.
To:	Oreilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML19207B505	List: ML19207B507 ML19207B509
References
NUDOCS 7908300087
Download: ML19207B509 (2)

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22 June 1979 Florida power c s _7 s _'13,3-o-5-m; Docket No.50-30J Mr. J. P. O'Reilly, Director License No. DPR-72 Office of Inspection & Enforcement Ref: RI I :T .TMel!

l'.S. Suelear Regulatory Comnission 50-302/74-13 101 Marietta St., Suite 3100 Atlanta, GA 30103

Dear Mr. O ' Re i l l ',

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'.i e offer the followin respon"c4 to t hi. appire nt 't in the ref erenced Inspec t ion ~:er, rt r NOT I C F OF 'J 1. 'I ..; 1 '.

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Plant Response to Enrineered Sate.uard,, withcut p r i .'r rertirs oi p l,in t :an gemen t .

A. R e sf on st; As stated in Sectien lua of the Detai:s in tht re oft about t re: cce 3F' Inspec t ion Re;, ort , SP 'il 7 was perforced at a temperat ure,  % 0' r Ae t xp' ti".e J instead of the required tempera'c.re between 200 anJ . a :' '

to the inspector, when thi, erro; vas d i s c ove ri ' '. thi ex t "t : t

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J. P. O'Reilly RII: JMcH/79'-13 f All concerned personnel have been cautioned that any variance from approved procedures must be implemented by approved procedural controls.

Compliance has been achieved this date.

3. As equired by Technical Specification 4.4.6.2.b, the Reactor Building sump inventory and discharge must be monitored at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

Contrary to the above, during the period of April 17-19,monitored 1979, thefor a period Reactor Building sump inventory and discharge were not of about thirty-five (35) hours.

B. Response- It was, at the time of the inspection, and at remains our conten-as o nitored The Reactor Building cump was t ion that no violation existed.

required and recorded as "off-scale high" on as thet s; heifsurp t lors for controls purn the time span in question, and no discharges were This madewas te prevent overflowin; were in " pull to lock" configuration.

the mistellaneous waste storage tank (WS7 ) whose level was at the iich alarr point.

The RCS leakage dete rminat ion does not utilize tha RB sump inventerv and Therefore, the di,charce to calculate the primary system leak rate.

nanitorinc. of the Rh sump, "off-scale high" neets the surveillance require-ment of Technic al Spec if icat ions.

There were two (2) alternatives to operatine this condition. Une was to shat down the plant, which would brce created additienal waste problers, and the other would have been to purp out the sump and overflow thi WST.

As neither of these two alternatives was acceptable, it was determined to accept the known high level in the Rh sump and to maintain discharges when spai e was available.

Should there be further questions, please contact us.

Very truly yours, FLORIDA POWER FORPORATIOS r

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