ML20024H397

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Ack Receipt of 910425 Response to Violations Noted in Insp Rept 50-213/91-06
ML20024H397
Person / Time
Site: Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date: 05/22/1991
From: Joyner J
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To: Mroczka E
CONNECTICUT YANKEE ATOMIC POWER CO.
References
NUDOCS 9106030255
Download: ML20024H397 (2)


See also: IR 05000213/1991006

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Docket No. 50-213

Connecticut Yankee Atomic Power Company

ATTN: Mr. E. J. Hroczka

Senior Vice President - Nuclear

Engineering and Operations

P.O. Box 270

Hartford, Connecticut 06141

Gentlemen:

,

Subject:

Inspection No. 50-213/91-06

This refers to your letter dated April 25, 1991, in response to our letter

dated March 19, 1991.

Thank you for informing us of the corrective and preventive actions documented

in your letter. These actions will be exanined during a future inspection of

your licensed-program.

Your cooperation with us is appreciated.

Sincerely,

Original 5:ened By:

Richard R Ke:rnig

James H. Joyner, Chief

Facilities Radiological Safety

and Safeguards Branch

Division of Radiation Safety

and Safeguards

CC:

W. D. Romberg, Vice President, Nuclear Operations

J. P. Stetz, Nuclear Station Director

G. H. Bouchard, Nuclear Unit Director

D. O. Nordouist, Director of Quality Services

R. M. Kacich, Manager, Generation Facilities Licensing

Gerald Garfield, Esquire

K. Abraham, PA0

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Public Document Room (PDR)

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Local Public Document' Room (LPDR)

Nuclear Safety Information Center (NSIC)

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J. Shediosky, SRI, Haddam Neck

W. Raymond, SRI, Millstone

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A. Wang, PM, NRR

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April 25, 1991

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Re:

10CFR2.201

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U.S. Nuclear Regulatory Commission

Attention: Document Control Desk

Washington, DC 20$$$

Gentlemen:

Haddam Neck Plant

Response to Notice of Violation

Inspection Report No. 50 213191-05

In'a letter dated March 19,1991,(I) the NRC Staff transmitted the results of

an inspection conducted at the Haddam Neck Plant from February 25 through

March 1,

1991.

In their inspection, the NRC Staff identified one Severity

Level IV violation concerning four instances where Connecticut Yankee Atomic

Power Company (CYAPCO) utilized the TN RAM shipping cask to transport licensed

material to the Barnwell disposal facility without performing the dryness

verification test at the specified vacuum condition, and requested that CYAPC0

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respond to the-Notice of Violation (NOV) within 30 days of the date of the

letter.

In a subsequent discussion with Mr. J. H. Joyner, CYAPC0 was granted

a 2 week extension in responding to the NOV.

Pursuant to the provisions of 10CFR2.201, CYAPC0 hereby provides its response

to the subject Notice 7f Violation in Attachment 1.

If you have any questions regcrding the information contained in this letter,

pleare contact us.

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Very truly yours,

CONNECTICUT YANKEE ATOMIC POWER COMPANY

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Senior Vice President

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cc:

T. T. Martin, Region 1 Administrator

J. H. Joyner, Chief, f acilities Radiological Safety and Safeguards Branch

A. B. Wang, NRC Project Manager, Haddam Neck Plant

J. T. Shedlosky, Senior Resident inspector, Haddam Neck Plant

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J. H. Joyner letter to E. J. Mrotzka, Inspection No. 50 213/91 06, dated

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March 19, 1991.

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Docket No. 10 113

AQ.9314

Attachment I

daddam Neck Plant

Response to Notice of Violation

Inspection Report No. 50 213/91 06

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April 1991

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U.S. Nuclear Regulatory Connission

A09434/ Attachment 1/Page 1

April 25, 1991

Haddam Neck Plant

Response to Notice of Violation

Inipsetion Report No. 50-&l3/91 01

Description of Violation

During an NRC inspection conducted on February 25 to March 1,1991, a viola-

tion of NRC requirements was identified.

In accordance with the " General

Statement of Policy and Procedure for NRC Enforcement Actions," 10 CFR Part 2,

Appendix C (1990), the violation is listed below:

10 CFR 71.12 states, in part, that " . . . a general license is hereby issued

to any licensee of the Commission to transport, or to deliver to a carrier for

transport, licensed material in a package for which a . . . certificate of

compliance . . . has been issued . . . this general license applies only to a

licensee who . . . complies with the terms and conditions of the . . . certif-

icate of compliance, as applicable, and the applicable requirements of Sub-

parts A, G, and H of this part. . . . "

Condition Number 8 of Certificate of

Compliance Number 9233, issued for the TN RAM shipping cask, states, in part,

that

. in

addition

to the

requirements

of

Subpart G of

10 CFR

"

. .

Part 71 . . . the package shall be prepared for shipment and operated in

accordance with the Operating Procedures of Section 7 of the applica-

tion. . . . "

Paragraph 7.1.2.31 of the Operating Procedures contained in the

Safety Analysis Report for the TN RAM shipping cask states, in part, that for

" . . . the cask dryness verification test . . . evacuate the cask cavity

until a stable vacuum of 10, +2,

0 mbar is indicated. . . . *

Contrary to the above, on March 16, March 26, April 3, and April 10 of 1990,

the licensee utilized the TN-RAM shipping cask to transport licensed material

to the Barnwell disposal facility, Barnwell, South Carolina, without perform-

ing the dryness verifit"40n test at the specified vacuum condition.

Specifi-

call,

on each occasion cited above, prior to releasing the cask from the

liceu Je's facility, the dryness verification test was performed, but at a

pressure of 13,15,17, and 15 mbar, respectively, for four shipments.

Root Cause

The root cause of this event was procedure inadequacy resulting from a lack of

clearly stated acceptance criteria in the dryness verification procedure.

This situation was further compounded by the failure of the operator to fully

understand the procedure.

In respense to a similar procedural discrepancy at

the Hillstone Nuclear Power Station on May 7,1990, an independent Corporate

Task Force was assembled to evaluate the adequacy of the dryntss verification

procedure.

Upon completion of its evaluation, the Task Force concluded that

the dryness verification procedure was inadequate in that there was no clearly

stated acceptance criteria in the procedure.

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U.S. Nuclear Regulatory Commission

A09434/ Attachment 1/Page 2

April 25, 1991

Based upon the findings of the Task force, procedure changes were implemented

by Waste Chem Corporation on May 25, 1990, to correct this procedural weak-

ness.

CYAPCO wishes to emphasize that the procedural inadequacy and resulting

violation of the casks certificate of compliance were self-identified at the

Haddam Neck Plant and procedure enhancements were implemented in a timely

manner to correct the discrepancy and preclude any future dryness verification

testing errors.

All of this work was completed well

before the NRC

inspection.

Further, it should be noted that the dryness verification testing

conducted in accordance with the faulted procedure had no adverse effect on

the waste form acceptance at the burial site.

CYAPCO considers a contributing factor to be the overreliance on the expertise

of the contractor, Waste Chem Corporation, regarding the technical adequacy of

the procedure.

Corrective Action

Upon discovery of the discrepancy, Waste Chem Corporation impicmented a

revision to tht. dryness verification procedure on May 25, 1990.

In addition,

CYAPC0 has reviewed its inventory of cask manuals to ensure compliance between

the cask certificate of compliance, cask safety analysis report, and cask user

procedures.

No additional discrepancies were identified.

Corrective Action to Prevent Recurrence

As a result of the Task Force findings, Waste Chem Corporation has initiated a

number of procedural changes and enhanced the training provided to its opera-

tors.

A precautionary note has been added to the procedure that cautions the opera-

tors regarding the interpretation of pressure plateaus in the cask dryness

,

verification and the potential that water may still be present in the cask at

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a higher pressure.

Further, any cask user procedures and procedure revisions

supplied by vendors will be verified using the certificate of compliance.

This verification will be completed before new procedures or revised proce-

dures are presented to the Plant Operations Review Committee for approval.

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Date by Which CYAPC0 Exoects to Achieve Fuli Compliance

The changes to the TN RAM procedures were completed on May 25, 1990.

Review of the inventory of vendor cask manuals was completed by CYAPC0 on

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April 5, 1991.

CYAPC0 considers our existing programs and procedures to be adequate and in

full compliance with applicable requirements.

Therefore, we conclude that

there is no programmatic deficiency at the Haddam Neck Plant with respect to

radioactive material handling and transportation.

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