05000245/LER-1996-064, :on 961220,previous Unit Director Did Not Meet TS Requirements.Caused by Failure to Comply with Approved Procedures.Qualifications of Current Millstone Unit 1 Director,Unit Operations Has Been Satisfactorily Documented

:on 961220,previous Unit Director Did Not Meet TS Requirements.Caused by Failure to Comply with Approved Procedures.Qualifications of Current Millstone Unit 1 Director,Unit Operations Has Been Satisfactorily Documented

ML20133P858
Person / Time
Site:	Millstone
Issue date:	01/20/1997
From:	Robert Walpole NORTHEAST NUCLEAR ENERGY CO.
To:
Shared Package
ML20133P856	List: 05000245/LER-1996-064, :on 961220,previous Unit Director Did Not Meet TS Requirements.Caused by Failure to Comply with Approved Procedures.Qualifications of Current Millstone Unit 1 Director,Unit Operations Has Been Satisfactorily Documented
References
LER-96-064, LER-96-64, NUDOCS 9701270129
Download: ML20133P858 (3)

LER-1996-064, on 961220,previous Unit Director Did Not Meet TS Requirements.Caused by Failure to Comply with Approved Procedures.Qualifications of Current Millstone Unit 1 Director,Unit Operations Has Been Satisfactorily Documented

Event date:
Report date:
Reporting criterion:	10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(viii) 10 CFR 50.73(a)(2)(ii) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
2451996064R00 - NRC Website

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l NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVLD BY OMB NO. 31604 104 (4 95)

EXPIRE 8 04/30!98 OL$E TION o ArlO R US 0

RS EPORTED L L'.'c"."' o^"l,o'"lf"l ^^ Mao 'adsla" alo"ff#'o %M LICENSEE EVENT REPORT (LER) 15W,^"o'? ',1cW;a",*/o?x",^&a'!8%5,,"#eo'"gayot"&

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F."CIUTY NAME l1)

DOCKET NUMBER (2)

PAGE (31 Millstone Nuclear Power Station Unit 1 05000245 1 of 3 TITLE H)

Previous Unit Director Did Not Meet Technical Specification Requirements EVENT DATE (6)

LER NUMBER (6)

REPORT DATE (7)

OTHER FACILITIES INVOLVED (8)

MONTH DAY YEAR YEAR SEQUENTIAL REVISION MONTH DAY YEAR FACILITY NAME DOCKET NUMBER NUMBER 12 20 96 96 064 00 01 20 97 OPERATINO THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR 5: (Check one or more) (11)

ODE m N

20.2201(b) 20.2203(a)(2)(v)

X 50.73(a)(2)(i) 50.73(a)(2)(viii)

POWER 20.2203(a)(1) 20.2203(a)(3)(i) 50.73(a)(2)(ii) 50.73(a)(2)(x)

LEVEL (10) 000 20.2203(a)(2)(i) 20.2203(a)(3)(ii) 50.73(a)(2)(iii) 73.71 20.2203(a)(2)(ii) 20.2203(a)(4) 50.73(a)(2)(iv)

OTHER D'

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20.2203(a)(2)(iii) 50.36(c)(1) 50.73(a)(2)(v) specif y in Abstract below

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20.2203(a)(2)(iv) 50.36(c)(2) 50.73(a)(2)(vii)

LICENSEE CONTACT FOR THIS LER (12)

NAME TELEP ONE NUMBER Onclude Area Code)

Robert W. Walpole, MP1 Nuclear Licensing Manager (860)440-2191 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13)

cAUSE

SYSTEM COMPONEN T M ANUF AC TURE R REPORTABLE

CAUSE

SYSTEM COMPONENT MANUFACTURER REPORTABLE TO NPRDS TO NPRDS 3:

SUPPLEMENTAL REPORT EXPECTED (14)

EXPECTED MONTH DAY YEAR SUBMISSION YES

'X~ NO (if yes. complete EXPECTED SUBMISSION DATE).

ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single-spaced typewritten hnes) (16)

On December 20,1996, with the plant in the COLD SHUTDOWN condition, an assessment of the training and qualifications of the previous Unit Director for Millstone Unit No.1 identified a violation of Technical Specification (TS) Section 6.3.1, Training. TS 6.3.1 requires the facility staff to meet or exceed the requirements of ANSI N18.1-1971 for comparable positions. The standard requires the Plant Manager (i.e. Unit Director) to have the experience and training normally required for examination for a Senior Reactor Operator (SRO) license or to designate an alternate with the proper qualifications. The assessment of the former Unit Director qualifications found no documentation of a training evaluation. Additionally, the individual did not have a designated alternate. This event was caused by a lack of procedure compliance. There were no actual safety consequences as a result of this event.

The safety significance of this event is that the Unit Director did not satisfy the requirements of ANSI N18.1. The individual was not qualified to review and approve changes to the facility design or procedures based on the conditions and limitations of the license for the unit.

As part of the corrective actions, the qualifications of the current Director, Unit Operations has been satisf actorily documented. Other corrective actions will include documentation of other Key Personnel and verification of the accuracy of the documents approved by the former Unit Director at Plant Operations Review Committee and Site Optrations Review Committee meetings.

9701270129 970120 PDR ADOCK 05000245-S PDR

1. =

NRC FpRM 36(IA U.S. NUCLEAR REGULATORY COMMISSION (4-95)

UCENSEE EVENT REPORT (LER)

TEXT CONTINUATION FACILfTY NAME (1)

DOCKET NUMBER (2)

LER NUMBER (6)

PAGE (3)

YEAR SEQUENTIAL REVISION Millstone Nuclear Power Station Unit 1 05000245 NUMBER NUMBER 2 of 3 96 064 00 TEXT (11more space is required, use additional copies of NRC m 366A) (11) j l.

Descriotion of Event On December 20,1996, with the plant in a COLD SHUTDOWN condition, an assessment of the former Unit Director's training and qualifications revealed that the TS Section 6.3.1 was violated. This assessment was the result of the NRC Senior Resident Inspector's request for documentation to support the qualifications of the former Unit Director. The assessment, completed on December 20,1996, determined that the records of an assessment of previous equivalent SRO training of the former director could not be located.

Procedure OA 1, " Organization, Responsibilities, and Assumption of Responsibilities for Key Site Personnel,"

is based on the license requirements of TS Section 6, " Administrative Controls." OA 1 identifies the training requirements for the Unit Director as 'Must hold a Senior Operator's License on his respective Unit or possess knowledge equivalent to that required to obtain a Senior Operator's License.'

Procedure TQ-1, Training and Qualification, specifies the controls for the Nuclear Training Department (NTD) training programs including the SRO training program. The Nuclear Training Manual, referenced by TQ-1, includes instructions for validation and documentation of equivalent knowledge.

The documentation requirements of procedure TQ-1 were not met. Specifically, the records required by procedure TQ-1 to document that the Unit Director had equivalent SRO knowledge do not exist.

ll.

Cause of Event

The cause of this event was f ailure to comply with the approved procedures.

On August 24,1995, an assessment by the Director, Quality and Assessment Services (QAS) of the former Unit Director's qualifications missed an opportunity to identify the lack of procedure compliance. The assessment stated that "A review of the qualifications of the new Director when compared to the requirements defined in ANSI N18.1, did not note any abnormalities."

lil. Analvsis of Event This event is reportable pursuant to 10CFR50.73(a)(2)(i)(B), any operation or condition prohibited by the plant's Technical Specifications. The procedures for establishing and documenting personnel qualification and training are adequate, but were not followed.

There were no actual safety consequences as a result of this event. The safety significance of this event is that the former Unit Director did not satisfy the requirements of ANSI N18.1. The individual was not qualified to review and approve changes to the facility design or procedures based on the conditions and limitations of the license for the unit.

N1tC FORM 360A (4-95)

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4 NRC FpMM 366A U.S. NUCLEAR REGULATORY COMMISSION (4 93)

UCENSEE EVENT REPORT (LER)

TEXT CONTINUATION FACILITY NAME (1)

DOCKET NUMBER (2)

LER NUMBER (6)

PAGE (3)

YEAR SEOuENTIAL REVISloN Millstone Nuclear Power Station Unit 1 05000245 NUMBER NUMBER 3 of 3 96 064 00 TEXT (If more space is required, use additional copies of NRC form 366A) (17)

IV. Corroclivalc11ons The qualifications of the current Millstone Unit No.1 Director, Unit Operations has been satisfactorily documented.

Northeast Nuclear Energy Company (NNECO) commits to verify and document the qualifications of other Key Personnel by January 31,1997.

NNECO commits to verify the accuracy of the documents approved by the former Unit Director at Plant Operations Review Committee and Site Operations Review Committee meetings. This verification will be conducted by grouping the documents by the systems that they affect and then completing the verification prior to declaring the individual systems operable.

Additionally, for the systems that are currently operable, NNECO commits to complete the verification i

by February 28,1997.

V.

Additional Information

This event and the corrective actions will be shared with Millstone Unit Nos. 2 and 3 for their applicability.

Similar Events

None Manuf acturer Data Not Applicable NRC FORM 360A (4 9b)

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