ML20054L726

Notice of Violation from Insp on 820105-0331

ML20054L726
Person / Time
Site:	Point Beach
Issue date:	06/22/1982
From:	Spessard R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20054L721	List: IR 05000266/1982001 ML20054L720 ML20054L726
References
50-266-82-01, 50-266-82-1, NUDOCS 8207080410
Download: ML20054L726 (2)

Text

I FILE COPY Appendix NOTICE OF VIOLATION Wisconsin Electric Power Company Docket No. 50-266 As a result of the inspection conducted on January 11, 1982, and in accordance with the NRC Enforcement Policy, 47 FR 9987 (March 9, 1982),

the following violations were identified:

1. 10 CFR 50.59 requires licensees to make written safety evaluations of changes in the facility as described in the safety analysis report to determine if the proposed changes involves a change in the technical specifications incorporated in the license or an unreviewed safety question.

Procedure PBNP 3.17, Revision 6, dated April 10, 1981, requires that changes in facility design as described in the FSAR be approved by the Manager and his Staff if the changes do not create the possibility of a type of accident not previously evaluated, and do not reduce the margin of safety as defined in the technical specifications. The j procedure also states "If the changes or additions cannot meet the above criteria, final approval rests with the Nuclear Regulatory Commission and the plant personnel will refer the item to the Nuclear Project Office for transmittal to the NRC."

Contrary to the above, on January 10, 1982, the licensee modified the steam pressure sensing system for the Unit 1A steam generator by moving the sensing point for the white channel from the steam header to the non-safety-related rad waste steam supply system without performing a safety evaluation of the change. The modi-fication resulted in the white channel transmitter sensing steam pressure from both the A and the B steam generators, contrary to

the requirements of Sections 7.2.3 and 14.2.5 of the Point Beach Final Safety Analysis Report, and may have compromised the ability of the white channel to sense a steam line break in the A steam

, generator.

This is a Severity Level IV violation (Supplement I).

4 8207080410 820622 PDR ADOCK 05000266 PDR Q

FILE COPY Appendix 2

2. Technical Specification 15.5.4.4 requires that for spent fuel storage "each storage location immediately adjacent to a wall shall be re-stricted to storage of fuel assemblies having a cooling time of one year or more."

Contrary to the above, from October 1 to November 3, 1981, fuel removed from Unit 2 in April 1981 was stored adjacent to the spent fuel pool divider wall and from November 3, 1981, to February 23, 1982, fuel removed from Unit 1 in October 1981 was stored adjacent to the spent fuel pool divider wall.

This is a Severity Level IV violation (Supplement I).

3. 10 CFR 50, Appendix B, Criterion XIV requires, in part, that, " Measures shall also be established for indicating the operating status of structures, systems, and components of the nuclear power plant or fuel reprocessing plant, such as by tagging valves and switches to prevent inadvertent operation." Operating Point Beach Nuclear Power Plant Administrative Control Policies and Procedures Manual Section 4.13,

" Equipment Isolation Procedure," is one of the measures established to satis fy the Appendix B requirement.

Technical Specification 15.6.8.1 requires, in part, that, "The plant shall be operated and maintained in accordance with approved procedures."

Procedure PBNP 4.13 Paragraph 5.4 requires that "the Duty Shift Super-visor shall have the equipment inspected and if it is satisfactory, he shall have the red tags removed by a qualified red tagger and the equipment lineup returned to normal."

Contrary to the above, on March 4, 1982, three red tags were removed from valves in the Unit 2 sampling room without the equipment being inspected and the equipment lineup was not returned to normal.

This is a Severity Level V violation (Supplement I).

Pursuant to the provisions of 10 CFR 2.201, you are required to submit to this of fice within thirty days of the date of this Notice a written statement or explanation in reply, including for each item of noncompliance: (1) cor-rective action taken and the results achieved; (2) corrective action to be taken to avoid further noncompliance; and (3) the date when full compliance will be achieved. Consideration may be given to extending your response time for good cause shown.

Dated R. L. Spessard, Director Division of Project and Resident Programs