ML20080K079

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Responds to NRC Re Violations Noted in IE Insp Rept 50-366/83-29.Corrective Actions:Relief Valve Operability Procedure Revised to Return to Tech Spec Testing Requirement & Plant Review Board Will Conduct Closer Review
ML20080K079
Person / Time
Site: Hatch Southern Nuclear icon.png
Issue date: 12/14/1983
From: Gucwa L
GEORGIA POWER CO.
To: James O'Reilly
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML20080K020 List:
References
NED-83-606, NUDOCS 8402150288
Download: ML20080K079 (2)


Text

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Georgia Power Company 333 Predmont Avenue Atlanta. Georg'a 30308 Teleptone 404 5266526 Meding Address:

f%f Office Box 4545 Atlanta Georg a 30302 7 n r !6 P 3 : il 9 Georgia Power L T. Gucwa the soutwo

  • x!nc sysvm Manager Nuclear Engineenng NED-83-606 and Chief Nuclear Eng neer December 14, 1983 U. S. Nuclear Regulatory Contaission REFERE!C2:

Office of Inspection.and Enforcement RII: ICL Region II - Suite 2900 50-366 r

101 Marietta Street, FM Inspection Report Atlanta, Georgia 30303 83-29 A'ITSNTION:

Mr. James P. O'Reilly GENITREN:

Georgia Power Conpany submits the followiry response to Inspection Report 50-366/83-29, concerning the inspection of Mr. R. V. Crlenjak during the period of August 20 to September 30, 1983. One violation was identified.

VIOIATION:

Technical Specification 6.5.1.6.a requires that the Plant Review Board (PRB) shall be responsible for review of all procedures required by Technical Specification 6.8 and changes thereto.

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Technical Specification 4.5.2 requites that the Automatic Depressurization System (ADS) shall be demonstrated operable by manually opening each ADS valve and observing that either; (1) the control valve or bypass valve positiot responds accordingly, or (2) there is a correspondence change in the measured steam flow.

T Contrary to the above, From April 1, 1982, until July 8, 1983, the

'Iwchnical Specification required method for ADS operational verification was not used.

%e procedure did prove operability br tailpipe pressure sensors to indicate opening of the relief valve; huver, the Technical Specifications do not recognize this method. On April 1, 1982, the PRB approved a change to procedure HNP-2-3901 (Rev. 7) that deleted the Technical Specification required method for ADS operability verification and substituted another method for verification.

On September 7, 1982 (Rev. 8), August 10, 1982 (Rev. 9), October 4, 1982 (Rev. 10), and on June 14,1983 (Rev.11, a general revision of the procedure), the PRB approved the procedure without the required method of ADS verification.

This is a Severity Level IV Violation.

IESPOPEE; Admission or denial of the alleged violation: The violation occured.

Reason for violation:

A design modification was ccznpleted adding pressure sensors to the SIN tailpipes.

Indication of tailpipe pressure 8402150288 840206 PDR ADOCK 05000366 G

PDR

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Georgia Power 1 U. S. Nuclear Regulatory Comnission Office of Inspection and Enforcement Region II - Suite 2900 December 14, 1983 P::ge Two RESPONSE: (Continued) provides a

reliable means of verifyirg proper SRV function.

Subsequently, the " Relief Valve Operability" procedure (HNP-2-3901) was revised to change the method of verification 'to use the newly installed pressure sensors.

Personnel did not realize that the revision would make the procedure fail to meet the requirements of Technical Specifications section 4.5.2.b, which specifies a different method of verifying SRV operability.

While it failed to meet the letter of the Technical Specifications, the new method fully met the intent of the subject Technical Specification, which was to verify operability of the SRVs. However, the requirements of Technical Specifications should have been more fully investigated prior to the procedure revision.

Corrective steps which have been taken and results achieved:

'Ihe

" Relief Valve Operability" procedure was revised on July 8, 1983 to return to the testing requirement delineated in the Technical Specifications. This procedure revision has been fully inplemented.

Corrective steps which will be taken to avoid future violations:

PRB menbers were made aware of this oversight as a result of LER 50-366/1983-39 and a review of the Inspection Report.

They hive been informed of the need for closer review of procedure changes proposed for safety-related systems which have a potential to impact Technical Specifications.

Date when full coupliance will be achieved:

Full compliance was achieved on July 8, 1983, when the procedure in question was revised to reflect Technical Specification Requirements.

If you have any questions, please contact this office.

Very truly yours, bS &

L. T. Gucwa REB /rb xc:

J. T. Beckham, Jr.

H. C. Nix, Jr.

Senior Resident Inspector, Plant Hatch 700775

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