ML20141E310

Notice of Violation from Insp on 970311-0519.Violation Noted:Since Commencement of Operations at Unit 1,applicable Regulatory Requirements & Design Basis Not Correctly Translated Into Drawings & Procedures

ML20141E310
Person / Time
Site:	Millstone
Issue date:	06/24/1997
From:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20141E286	List: ML20141E283 ML20141E310 ML20141E341
References
50-245-97-02, 50-245-97-2, 50-336-97-02, 50-336-97-2, 50-423-97-02, 50-423-97-2, NUDOCS 9707010028
Download: ML20141E310 (2)

Text

( *s ENCLOSURE 1 NOTICE OF VIOLATION Northeast Nuclear Energy Company Docket Nos.: 50-245; 50-336; 50-423 Millstone Nuclear Power Station License Nos.: DPR-21; DPR-65; NFP-49 Units 1, 2, and 3 During an NRC inspection conducted on March 11,1997 through May 19,1997, violations of NRC requirements were identified. In accordance with the " General Statement of Policy and Procedure for NRC Enforcement Actions," NUREG-1600, the violations are listed below:

A. 10 CFR 50, Appendix B, Criterion Ill, Design Control, requires measures to be established to assure that applicable regulatory requirements and the design basis are correctly translated into specifications, drawings, procedures, and instructions.

Contrary to the above, since commencement of operations at Unit 1, applicable regulatory requirements and the design basis were not correctly translated into drawings and procedures in that: (1) Updated Final Safety Analysis Report Figure 6.2-15 and plant drawings 25202-20290 and 25202-20002 incorrectly showed a bottom drain connection on feedwater system piping downstream of check valves 1-FW-10A and 1-FW-10B; (2) branch lines containing manual isolation valves 1-FW-107A and 1-FW-107B located downstream of check valves 1-FW-9A and 1-FW-9B were not shown on drawings 25202-29119, 25202-20290, 25202-20002, or 25202-29013; and, (3) valves 1-FW-107A and 1-FW-107B were not included in Operations Instruction 1-OPS-10.11, " Locked Valve List," and the valves were not locked in the closed position as required.

This is a Severity Level IV violation (Supplement l} for Docket No. 50-245.

B. 10 CFR 50, Appendix B, Criterion XVI, requires that measures be established to assure that conditions adverse to quality, such as deficiencies, deviations, and nonconformances are promptly identified and corrected.

Contrary to the above, at Unit 2, the licensee failed to adequately identify and correct a deficiency with Alarm Response Procedure (ARP) 2590H,

" Alarm Response for Control Room Radiation Monitor Panels, RC-14," Alarm RC-14C, " Unit 2 Stock Gaseous" This ARP deficiency failed to ensure that the main exhaust fans were secured in response to alarm RC-14C, as was documented in Licensee Event Report (LER) 94-40, Revision 2, dated September 11,1995. The NRC decision to not backfit the licensee to address the single failure vulnerability discussed in the LER was based heavily on the operator compensatory action described in LER 94-40, Revision 2, involving securing the main exhaust fans in response to the Unit 2 stack radiation monitor alarm.

This is a Severity Level IV violation (Supplement l} for Docket No. 50-336.

9707010028 970624 PDR ADOCK 05000245 0 pun

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C. Title 10, Code of Federal Regulations, Part 20.1101 (a) (10 CFR 20.1101 (a))

requires, in part, that licensees davalop and implement a radiation protection program. Paragraph 1.1 of procedure RPM 5.22, " Basic Radiation Worker Responsibilities," requires, in part, that workers entering the radiologically controlled areas (RCAs) comply with instructions provided by the unit radiation protection staff, including those instructions contained in radiation work permits (RWPs). All )

entries to the RCA require that individuals be signed in on a general or specific radiation work permit (RWP) and wear a functioning digital alarming dosimeter and thermoluminescent dosimeter (TLD).

Contrary to the above, five instances of personnel entering the RCA without wearing a functional electronic dosimeter or TLD were identified. These include one

, instance in Unit 1 on April 15,1997; three instances in Unit 2, one each on March 5,1997, March 7,1997, and April 15,1997; and one instance in Unit 3 on April 29,1997.

This is a Severity Level IV violation (Supplement IV) for Docket Nos. 50-245, 50-336, & 50-423.

Pursuant to the provisions of 10 CFR 2.201, Northeast Nuclear Energy Company is hereby required to submit a written statement or explanation within 30 days of receipt of the letter transmitting this Notice of Violation (Notice) to the U.S. Nuclear Regulatory Commission,

, ATTN: Document Control Desk, Washington, D.C. 20555 with a copy to the Director, Special Projects Office, Nuclear Reactor Regulation, and a copy to the NRC Resident  ;

inspector at the facility that is the subject of this Notice. This reply should be clearly l marked as a " Reply to a Notice of Violatior ' and should include for each violation: (1) the  !

reason for the violation, or, if contested, tne basis for disputing the violation, (2) the

corrective steps that have been taken and the results achieved, (3) the corrective steps that will be taken to avoid further violations, and (4) the date when full compliance will be achieved. Your response may reference or include previous docketed correspondence, if the correspondence adequately addresses the required response, if an adequate reply is not received within the required time specified in this Notice, an order or a Demand for 2 Information may be issued as to why the license should not be modified, suspended, or revoked, or why such other action as may be proper should not be taken. Where good cause is shown, consideration will be given to extending the response tirne.

Dated at King of Prussia, Pennsylvania j this 24th day of June,1997

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