ML20236K740

Ack Receipt of 870929 Ltr Informing NRC of Steps Taken to Correct Deficiency Noted in Insp Rept 50-267/87-19

ML20236K740
Person / Time
Site:	Fort Saint Vrain
Issue date:	11/04/1987
From:	Callan L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:	Robert Williams PUBLIC SERVICE CO. OF COLORADO
References
NUDOCS 8711090332
Download: ML20236K740 (2)

See also: IR 05000267/1987019

Text

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In Re. ply Refer To:

Docke t: 50-267/87-19

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Public Service Company of Colorado

ATIN: Robert C. Williams, Jr.

Vice President, Nuclear Operations

2420 W. 26th Avenue, Suite 15c

Denver, Colorado 80211

Gentlemen:

Thank you for your letter of September 29, 1987, in resp'onse to our letter

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and deficiencies dated August 28, 1987. We have reviewed your reply and find

it responstve to the concerns raised in our Inspection Report. We will review

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the. implementation of your corrective actions during a future inspection to

determine that full compliance has been achieved and will be maintained.

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Sincerely,

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Leonard J. Callan, Director

Division of Reactor Projects

cc:

Manager, Nuclear Production Division

Fort St. Vrain Nuclear Station -

16805 WCR 19h

Platteville, Colorado 80651

F. Tomlinson, Manager, Quality

Assurance Division

(same address)

De. F. Shoemaker, Education Specialist

FEMA Region 8

Denver Federal Center Bldg. 710 q

Box 25267

Denver, Colorado 80225-0267

Colorado Radiation Control Program' Director

Colorado Public Utilities Commission

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' September 29, 1987. R.O. WILT. LAMS, JR.

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vicE PRESIDENT

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Unit No. 1 NUCLEAR OPERATIONS f f[j

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P-87343:

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REFERENCE: I&E Inspection Report .j

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-87-19 (G-87289) i

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. . ' Gentlemen:

<L , Attached are:the Public Service Company responses to the deficiencies

. identified within I&E' Inspection . Report 87-19. If you have any

questions or comments associated with these responses, please call

Mr. M. H. Holmes at (303) 480-6960.

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Sincerely,

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R. O. Williams, Jr.

Vice President, Nuclear Operations

i- Fort St. Vrain Nuclear

Generating Station

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Attachment

cc: Regional Administrator, Region IV

Attention: Mr. J. E. Gagliardo, Chief

Reactor Projects Branch

(2 copies)

Mr. R. E. Farrell

Senior Resident Inspector

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Fort St. Vrain

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Attachment to P-87343 -2- September 29, 1987

RESPONSE TO DEFICIENCIES

267/8719-01: Insufficient direct radiation and radiofodine

measurements were made by off site field teams to

support confirmation of dose assessment calculations.

PSC Response: There was. a. problem with the A/C power indicator and

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locking device associated with the inverter in one of >

the RERP field vehicles which resulted in

uncontrollable voltage output. This, in turn, caused

the air sa apler motor to trip and resulted in the

inability to collect air samples.

.The problem was evaluated by Plant Electricians and

found to require more sophisticated diagnostics. The

i vehicle is now being repaired at the corporate fleet

maintenance facility. Backup sampling equipment,

.which may be used in the event that a primary air

.- sampler 'becomes inoperable, is currently being

evaluated. Backup air sampling capabilities will be

obtained and appropriate personnel trained in their

use by December 31, 1987.

267/8719-02: Procedure RERP-PCC was not followed, in that the

frisker and control point specified in Attachment A to

l that procedure were'not established when the PCC was

activated.

PSC Response: The Personnel Control Center (PCC) layout identified

in Attachment A of RERP-PCC, Issue 18, has been

re-evaluated to determine the mest efficient use of

equipment and space available. The layout will be

changed to reflect this evaluetion. Also, the

procedure will be revised to include a copy of the

layout as part of Checklist E.a, the " Physical Set Up

Checklist". This is to ensure that the layout is

followed more closely. During training, emphasis will

continue to be placed on the importance of

understanding and. following established procedures.

The RERP-PCC procedure revision will be completed and

all PCC personnel made aware of the revision by

December 31, 1987,

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.Attachmelt -3-- September 29, 1987

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267/8719-03: Procedure RERP-Survey was not followed, in that'two

persons were not dispatched 'to obtain a reactor

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, coolant sample as required by procedure RERP-Survey.

PSC Response: Ouring the conduct of F0SAVEX-87, one of the

activities identified by the. Technical Support Center

(TSC) staff to be performed was to obtain a " Post

Accident Sample of Primary Coolant" from the High i

Temperature Filter Absorber sample line to assess fuel

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, damage. . Preparation.of a team briefing by a Health

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Physicist .in the TSC was initiated. Two Health

Physics (HP) Technicians were directed to the HP

Operations office in order to receive the briefing and

subsequent dispatch.

Both- HP Technicians dressed out demonstrating

knowledge of appropriate procedures. Upon completion

of the briefing, for reasons outside the scope of the

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exercise, one of the HP Technicians was required to

leave the site. At this point, it was decided to

simulate his presence on the entry team. Due to

inadequate communications with exercise controllers,

exercise evaluators were not made aware of this

simulation. Therefore, it was not apparent upon entry

to the reactor building that two persons were

entering, one being simulated.

The deficiency is a result of the players' failure to

inform appropriate personnel of the situation. The

players involved have been instructed on the

importance of proper communication of exercise

activities, especially simulations. Suitable

controller / player interaction will continue to be

stressed during center training and drilling. No

further action is considered necessary for this item.

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Attachment to P-87343 -4- September 29, 1987

267/8719-04: Procedure RERP-MEP was not followed, in that the

injured person was not appropriately marked and tagged

as required.

PSC Response: This deficiency is limited to the Health Physics .

actions taken and was identified in the licensee's QA  :

audit. In the response to QDR 87-080 which documented  :

this deficiency, a Training Development Request (TDR)

was initiated to provide retraining on emergency

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contamination and control practices to HP staff

A lesson plan is currently being developed,

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members. {

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and all HP personnel will be trained on it by December 1

31, 1987. *

The need for a Health Physics response kit has been

evaluated and determined to be of significant benefit

to persons responding. A kit will be established

following development of kit specifications.

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Further enhancements to the. program include rewriting

the Medical Emergency Plan and training appropriate

personnel in its use. At present, actions have been

initiated with the primary response hospital (St.

Luke's) to rewrite the agreement held by FSV and the

hospital. Once a new agreement has been reached, the

Medical Emergency Plan will be rewritten to make it

more concise and usable. Upon completion, appropriate

personnel will be trained in its use. The

enhancements are anticipated to be completed and

implemented by April 18. 1988.

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Items identified by plant personnel during the post-exercise critique l

(as outlined in Item 8 of the referenced NRC report) have been

reviewed and appropriate corrective actions initiated, as required.

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