ML19339A920

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Responds to NRC Re Violations Noted in Insp Rept 50-029/74-16.Corrective Actions:Failure to Meet Setpoint Criteria to Be Reported Per Tech Specs,Drawings Control Procedure Being Prepared & Contractors Sought
ML19339A920
Person / Time
Site: Yankee Rowe
Issue date: 02/07/1975
From: Heider L
YANKEE ATOMIC ELECTRIC CO.
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML19339A918 List:
References
WYR-75-15, NUDOCS 8011050702
Download: ML19339A920 (3)


Text

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I f'3 Telephone bl7 366-90ll v'

TirI 780 390 0739

. ANKEE ATOMIC ELECTRIC COMPANY m,s-15

,Ms.N 20 Turnpike Road Westborough, Massachusetts 01581 NKEE February 7, 1975 United States Nuclear Regulatory Commission Region I 631 Park Avenue King of Prussia, Pennsylvania 19406 Attention: Office of Inspection and Enforcement

Reference:

1) License No. DPR-3 (Docket 30. 50-29)
2) AEC Inspection Report No. 50-29/ 1-16, dated January 10, 1975

Dear Sir:

This letter is written in response to your letter dated January 10, 1975, Reference 2, which indicates that five items appeared to be in violation of AEC requirements. These items were reported as a result of an inspection conducted on December 18, 19, and 20, 1974 at the Yankee Facility in Rowe, Massachusetts.

Information is submitted in answer to the alleged violations contained in Enclosure 1 of your letter as follows:

A.

Category II Violations 1.

No response required.

2.

Technical Specification E.4.n. classifies as an abnormal occurrence. "A safety system setting less conservative than the limiting setting established in the technical specifi-cations." Technical Specification E.2.a. states in part that in the event of an abnormal occurrence, "A notification shall be made within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />...to the Director of the Regional Regulatory Operations Office."

Contrary to the above, a reactor trip setting on one of two main coolant low flow trip circuits was not reported as an abnormal cccurrence when found by the licensee on July 15, 1974, to be set less conservatively than the safety system setting established by the licensee.

e 110 ti 0 $2*C0)$ d.

.i United States Nuclear Regulatory Commissior February 7,-1975' Attn: Office of Inspection and Enforcement Page Two j

Response

Plant instrument supervisory personnel have been reminded that

' all instances of failure to meet the satpoint criteria of safety related surveillance procedures must ne reported to the Plant Superintendent, or his designated alternate, for. evaluation. In the future similar findings will be reported in accordance with-the Technical Specifications.

1 3.

Cr.ss_.on VI of Appendix B to 10 CFR 50 states in part:

" Measures shall be established to control the issuance of documents, such as... drawings, including changes thereto, which prescribe all activities affecting quality. These measures shall assure that documents, including changes, are reviewed for adequacy and approved for release by I

authorized personnel and are distributed to and used at the location where the prescribed activity is performed..."

1 Additionally, QA procedure WO-105, " Procedures, Drawings and Specifications," requires in part that plants are to be responsible for the accuracy of their drawings.

Contrary to the above, an approved plant procedure to control the issuance of drawings including changes thereto did not exist. Additionally,-3 drawings in the plant files (drawings l

' 517 F C69, 9699-FK-1A, and 9699-FM-3A) had not been revised to include the changes required by PDCR 74-3 which was completed on July 30, 1974. We note that the 3 drawings described above were ' revised to include the appropriate changes prior to the completion of this inspection.

Response

It is acknowledged that the plant has not completed preparation of a procedure to control plant drawings due to the greater priority need to develop several hundred operational procedures to comply with previous AEC sudits.

The size of the plant and the intimate knowledge of plant system details'by the Department Heads would preclude using the unchanged drawings in the preparation of Design Changes.

The normal process of revising drawings in the plant files requires l

forwarding a. marked up drawing to NSD Operations for updating of the I

master drawing which is then sent to a commercial organization for j

reproduction. Corrauced copies are then forwarded to the plant. Due to e variable ~ workload at' all these locations this process may take -

several months.

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i United States Nuclear Regulatory Commission February 7, 1975 Attn: Office of Inspection and Enforcement Page Three 4.

Criterion XII of Appendix B to 10 CFR 50 states ir part:

" Measures shall be established to assure that... measuring end testing devices used in activitiss affecting quality are properly... calibrated..."

Contrary to the above, requirements have not been established by the plant to obtain and document "aa-found" conditions for measuring and testing equipment calibrated off site. This is considered to be an improper calibrating measure in that it does not allow the plant to determine when instruments have been found to be out of calibration.

Response

The plant has requested an "as-found" calibration from off site contractors in the past with little success. Additienal efforts will be made to locate contractots who will provide this service.

B.

Category III Violations 1.

Criterion V of Appendix B to 10 CFR 50 states in part:

" Activities affecting quality shall be... accomplished in accordance with... instructions, procedures, or drawings."

Contrary to the above, the following are examples of failure to follow established procedures:

(a) Changes were made to procedures OP-6101, RP-1601, and OP-6000.16 without being approved by two Senior Licensed Cperators as is required by procedure AP-0001.

Response

The cognizant Department Heads have been reminded that under the requirements of Revision 2 of AP-0001 temporary changes to approved procedures that do not change the intent of the procedure cannot be,

made without the approval of two senior reactor operator licensees.

1.(b) No response required.

We trust you will find this information satisfactory; however, should you desire additional information feel free to contact us.

Very truly yours, YANKEE ATCMIC ELECTRIC CCMPANY L. H. Heider Manager of Operations REMR/kg e

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