ML20207J400

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Notice of Violation from Insp on 860929-1114
ML20207J400
Person / Time
Site: Byron  Constellation icon.png
Issue date: 12/31/1986
From: Paperiello C
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20207J204 List:
References
50-455-86-34, NUDOCS 8701080432
Download: ML20207J400 (2)


Text

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NOTICE OF VIOLATION Comonwealth Edison Company Docket No. 50-455 As a result of the inspection conducted on September 29 through November 14, 1986, and in accordance with the " General F111cy and Procedures for NRC Enforcement Actions," 10 CFR Part 2, Appendix C (1986), the following violation was identified:

10 CFR 50, Appendix B, Criterion XI, as implemented by the Comonwealth Edison Company's Quality Assurance Manual, Quality Requirement 11.0, requires that test results be documented and evaluated to assure that requirements have been met.

Comonwealth Edison Company's Quality Assurance Manual, Quality Procedure i No.11-2, requires that the documentation of pre-operational tests include a list of any apparent deficiencies.

Byron Startup Manual, Paragraph 4.7.3.7, requires that deficient conditions discovered during testing be recorded as deficiency drafts.

Technical Staff Memorandum (TSM) T03.03A implements these requirements and requires that when a System Test Engineer (STE) identifies a problem with a system during the performance of a test (i.e. data outside expected range, incorrect indications, etc.) the STE will document the problem in a deficiency draft.

Byron Startup Manual, Paragraph 4.1.4 requires that deficient conditions be documented on deficiency record forms.

Contrary to the above:

a. Byron Preoperational Test CV 18.61, " Chemical and Volume Control, Charging, Letdown and Reactor Coolant Pump Seal Injection Logic Test," Step 9.0.3 requires that Local and Main Control Board timed valve responses be within 20%

of each other.

l On November 11, 20, and 21, 1985, the STE failed to initiate deficiency i drafts when Step 9.0.3 determined that the difference between remote

! versus local timing values exceeded 20% for valves 2CV8160, 2CV0459, and 2CV8149C, respectively.

b. Byron Preoperational Test RY 69.67, " Pressurizer (Integrated Hot Functional),"

Step 9.5.18, requires that power operated relief valve discharge line surface temperatures be measured and recorded at 30 minute intervals until the temperatures stabilize.

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Notice of Violation 2 On May 30, 1986, the STE failed to initiate a deficiency draft for a Power Operated Relief Valve (PORV) discharge line temperature spike and to draft a deficiency noting that PORV discharge line temperatures had not been measured and recorded until the temperature had stabilized for PORV 2RY455A.

c. Byron Preoperational Test RH 67.60, " Residual Heat Removal System,"

Section 13, Appendix C, requires verification of four plant operating procedures pertaining to the residual heat removal system.

Prior to February 19, 1986, when the test package was closed, the STE failed to initiate a deficiency draft for plant operating procedures which were not verified during the performance of RH 67.60.

This is a Severity Level V violation (Supplement II) (455/86034-01(DRS)).

Pursuant to the provisions of 10 CFR 2.201, you are required to submit to this office within thirty days of the date of this Notice a written statement or explanation in reply, including for each violation: (1) corrective action taken and the results achieved; (2) corrective action to be taken to avoid further violations; and (3) the date when full compliance will be achieved.

Consideration may be given to extending your response time for good cause shown.

/d- Sl* tb w Date Capf J.papepiello, Dfrector Di4ision of4eactor Safety 9

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