ML20137F630

Notice of Violation from Insp on 970119-0222.Violation Noted:Design Control Requirements Not Translated Into Specifications

ML20137F630
Person / Time
Site:	Hatch
Issue date:	03/24/1997
From:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20137F607	List: ML20137F603 ML20137F630 ML20137F645
References
50-321-97-01, 50-321-97-1, 50-366-97-01, 50-366-97-1, NUDOCS 9704010168
Download: ML20137F630 (4)

Text

1 NOTICE OF VIOLATION i Southern Nuclear Operating Docket Nos. 50-321, 50-366

. Company, Inc. License Nos. DPR-57, NPF-5  !

Hatch Units 1 and 2 .

During the NRC inspection conducted on January 19, 1997 through February 22, .

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 III Design Control, requires, in ,

part, that measures shall be established to assure that applicable ,

regulatory requirements for th:: a structures, systems. and components to which this appendix applies are correctly translated into specifications, drawings, procedures, and instructions. J Contrary to the above, design control requirements were not I translated into specifications in that, on January 29, 1997, it- i was discovered that the required dimensions of a welded pipe and  :

valve installation, as documented on drawing S-01286, were not I correctly translated into a replacement installation during the l Spring 1996 refuelling outage of Unit 1. l This is a Severity Level IV Violation (Supplement 1) (Unit 1). ]

B. Technical Specification 5.4 requires that written procedures be  :

established, implemented, and maintained covering activities delineated in appendix A of Regulatory Guide (RG) 1.33. Revision  ;

(Rev.) 2. February 1978. '

i Regulatory Guide 1.33, Appendix A: Typical Procedures for 1 Pressurized Water Reactors and Boiling Water Reactors,

)aragraph 1.d. recommends procedures for Procedural Adherence.

)aragraph 1.a recommends procedures for Security; paragraph 1.k i recommends procedures for the Plant Fire Protection Program: and l paragraph 8.b recommends procedures for Calibrations.  !

Procedure 42CC-ERP-011-05, Control Rod Exchange, Rev. 8, provides instructions for control rod sequence exchanges and for Rod Worth Minimizer Mode changes. Procedure section 7.2.28 provided instructions to ensure the Rod Worth Minimizer instrumentation was properly selected for the correct Rod Sequence Mode.

Procedure 40AC-ENG-008-0S, Fire Protection Program Rev. 8.

step 8.1.2.2, states, in part, that unattended storage of any transient fire load in a safety related area required a Transient Combustible Permit.

Enclosure 1 9704010168 970324 PDR ADOCK 05000321 G PDR 1

L

Notice of Violation 2 Procedure 57CP-CAL-108-IS. General Electric Type IAC and Westinghouse Type C0 Relays. Rev. 9. provides instructions for

)erforming a calibration of Type IAC and Type C0 Overcurrent Relays. Attachment 2 of the procedure and the Relay Data Sheet for the 4-kV Bus IF1 supply transformer provide the calibration settings for the bus relays.

Procedure 31GO-0PS-011-0S FHA Operating Requirements. Rev. O.

establishes the compensatory measures to be taken for degraded fire protection components. This includes a required hourly fire watch for inoperable or degraded fire barrier assemblies.

Procedure 82SS-SEC-022-5S, Security Department Equipment Inventory. Rev. 2. requires an equipment inventory at a designated frequency. Procedure 82SS-SEC-027-55. Compensatory Officer Turnover Report. Rev. 4. referenced Security Operations Order 96-01. dated January 31, 1996, which requires security personnel to conduct a " hands on" (touch) inventory of security weapons at a designated frequency.

Contrary to the above, procedures were not implemented in that:

1. On January 29, 1997, i.he Rod Worth Minimizer Instrumentation was monitoring the B2 Rod Sequence Mode when it should have been monitoring the B1 Rod Sequence Mode. The Rod Worth Minimizer Instrumentation was not monitoring the correct rod sequence in accordance with Section 7.2.28 of procedure 42CC-ERP-011-0S.

2. On February 12, 1997. Procedure 40AC-ENG-008-0S was not implemented in that approximately 40 to 45 unattended metal 55-gallon drums containing used oil, oil-water mixture and oil sludge were stored at the 112-foot elevation of the control building in fire zone 0007A. a safety-related area, without a Transient Combustible Permit.

3. On February 4. 1997. Overcurrent Relays IS32-K217-1. -2 and

-3 were not adjusted to the pro)er settings in accordance with the Relay Data Sheet for t1e 4-kV Bus IF1 su) ply transformer and Attachment 2 of procedure 57CP-CA -108-15.

4. From January 16 through January 31, 1997. Procedure 31GO-0PS-011-0S was not implemented in that hourly fire watch patrols required for an inoperable fire rated assembly in the cable spreading room. Fire Area 24A, were not performed.

i Enclosure 1

4 Notice of Violation 3

5. On February 19, 1997, a " hands on" (touch) inventory of security weapons was not conducted at a designated frequency e in accordance with Procedure 82SS-SEC-027-5S and Security Operations Order 96-01. As a result, an unattended security weapon was not detected for about 11 hours1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br />.

This is a Severity Level IV Violation (Supplemen+ 1).

i C. 10 CFR 50, Appendix 8. Criterion V. Instructions, Procedures and Drawings, requires that activities affecting quality shall be '

prescribed by documented instructions, procedures, or drawings of  :

a type appropriate to the circumstances and shall be accomplished in accordance with these instructions, procedures, or drawings.

Instructions, procedures or drawings shall include appropriate qualitative acceatance criteria for determining that important activities have 3een satisfactorily accomplished.

Contrary to the above, on January 25, 1997, activities affecting

! quality were not adequately prescribed in that Instrumentation and Control technicians were calibrating a time delay relay associated l with the Unit 2 High: Pressure Coolant Injection (HPCI) System with an inadequate procedure. Procedure 57CP-CAL-051-2S. Rev. 7, failed to identify system response due to the relay calibration activity. As a result, unexpected annunciators were received: a 3rimary containment isolation valve inadvertently closed: and the iPCI system was made inoperable during the performance of-the procedure.

This is a Severity Level IV Violation (Supplement I) (Unit 2).

l D. Technical Specification Section 5.4.1.d states that written procedures shall be established, implemented, and maintained l

covering the fire protection program implementation.

l FHA, Section 9.2. Appendix B. Item 1.1.1, states that fire-rated assemblies and sealing devices in fire rated assembly penetrations

! separating fire areas or separating portions of redundant systems important to safe shutdown within a fire area shall be OPERABLE.

FHA, Section 9.2, Appendix B. Item 1.1.1. Action Item b requires the licensee to restore the inoperable fire-rated assembly (s) and or sealing devices to OPERABLE status within 14 days, or prepare and submit a special report to the Safety Review Board within the next 30 days.

4 Enclosure 1 l

i.

I Notice of Violation 4 Contrary to the above. as of January 31, 1997, a special report had not been submitted to the Safety Review Board to address.two degraded electrical raceway )enetration through the 3-hour fire wall separating the control )uilding from the east cable way on ,

the 112-foot elevation of the control building. These  :

penetrations had been inoperable since November 3. 1995.

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

l Pursuant to the provisions of 10 CFR 2.201, Southern Nuclear Operating 1 l Company, Inc. is hereby required to submit a written statement or e.xplanation to the U.S. Nuclear Regulatory Commission ATTN: Document Control Desk. '

l Washington, D.C. 20555, with a copy to the Regional Adminis+.rator, Region II, i i and a copy to the NPC Resident Inspector Hatch Nuclear Plant, within 30 days  :

i of the date of the letter transmitting this Notice of Violation (Notice). This reply should be clearly marked as a " Reply to a Notice of Violation" and

, should include for each violation: (1) the reason for the violation, or, if contested, the 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 com)liance will be achieved. Your response may reference or include previous clocceted correspondence, if the correspondence adequately addresses the  ;

required response. If an adequate reply is not received within the time specified in this Notice, an order or Demand for Information may be issued as  ;

to why the license.should not be modified, sus) ended, or revoked, or why such  !

other action as may be proper should not be tacen. Where good cause is shown.

consideration will be given to extending the response time.

Because your res)onse will be placed in the NRC Public Document Room (PDR), to the extent possi ale, it should not include any personal privacy )roprietary, or safeguards information so that it can be placed in the PDR witlout ,

redaction. However, if you find it necessary to include such information, you

• should clearly indicate the specific information that you-desire not to be placed in the PDR. and provide the legal basis to support your request for withholding the information from the public.

Dated at Atlanta, Georgia this 24th day of March 1997 I

l Enclosure 1 l

8