ML17055D167

Forwards Comments Re 870706 Scenario for 870826 Partial Scale Emergency Exercise.Remaining Clarification May Be Discussed at Briefing Prior to Drill

ML17055D167
Person / Time
Site:	Nine Mile Point
Issue date:	08/24/1987
From:	Lazarus W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:	Chwalek T NIAGARA MOHAWK POWER CORP.
References
NUDOCS 8709010132
Download: ML17055D167 (10)

Text

ACCESSION NBR FACIL: 50-410 AUTH. NAME LAZARUS i W. J.

RECIP. NAME CHWALEKt T.

I EQL ORY INFORMATION DISi%IBU SYSTEM

( R IDS

)

8709010132 DOC. DATE: 87/08/24 NOTARIZED:

NO Nine Mile Point Nuclear Stations Unit 2i Niagara Moha AUTHOR AFFILIAI ION Region li Office of Director RECIP IENT AFFILIATION N'agara Mohawk Power Corp.

DOCKET 05000410

SUBJECT:

Forwards comments re 870706 scenario for 870826 partial scale emergencg exercise. Remaining c jarification may be discussed at briefing prior to drill.

DISTRIBUTION CODF:

IE35D.

COPIES RECEIVED: LTR ENCL SIZE:

TITLE: Emergency Preparedness-Appraisal/Confirmatory Action Ltr/Exercise Rep NOTES: 21 05000410 REC IP IENT ID CODE/NAME PD1-1 PD BENEDICT. B COPIES LTTR ENCL 1

1 REC IP 1ENT ID CODE/NAME HAUGHEYi M COPIES LTTR ENCL 1

INTERNAL: ARM/DAF/LFMB NRR/PMAS/ ILRB RGN1 FILE 01

'EXTERNAL:

LPDR NSIC 1

0 1

1 1

1 11, 1

NRR/DREP/EPB 02 2/DRSS/EPRPB NRC PDR 1

1 1

1

.<t l

i)

C TOTAL NUMBER OF COPIES REQUIRED:

LTTR 12 ENCL 11

e ~

~ ~

J

/

0 ~

~ ~

AUG 24

)gory Docket Nos.

50-220 50-410 Niagara Mohawk Power Corporation ATTN:

T. Chwalek Emergency Coordinator 301 Plainfield Road

Syracuse, New York 13212 Gentlemen:

Subject:

Nine Mile Unit 2 Emergency Exercise Review Comments This is in response to the letter of July 6, 1987 transmitting the scenario for the partial-scale exercise scheduled for August 26, 1987.

We have reviewed the exercise package and provide the enclosed comments.

These comments were discussed by telephone on July 27, 1987 with you and members of my staff.

Any remaining clarification may be discussed at the briefing prior to the drill.

Should you have any questions in regard to our review, contact Mr. T.

Tuccinardi (215) 337-5390 or Mr. E.

Fox (215) 337-5044.

Sincerely, pz gr~in 1 Signed Byt

Enclosure:

As stated William J. Lazarus, Chief Emergency Preparedness Section Division of Radiation Safety and Safeguards OFFICIAL RECORD COPY 8709010132 870824 PDR ADOC< 05000410 F

PDR

~ ~

~ ~

~

~ ~

cc w/encl:

T.

E. Lempges, Vice President, Nuclear Generation T. Perkins, General Superintendent, Nuclear Generation M. Hansen, Manager of guality Assurance J.

A. Perry, Vice President, guality Assurance T.

Roman, Station Superintendent J. Aldrich, Supervisor, Operations M. Drews, Technical Superintendent Troy B. Conner, Jr., Esquire John M. Keib, Esquire

Director, Power Division Conner 5 Metterhahn D. guamne, NMP-2 Project Director C. Beckham, NMPC gA Manager R. B. Abbott, Station Superintendent Department of Public Service, State of New York Public Document Room (PDR)

Local Public Document Room (LPDR)

Nuclear Safety Information Center (NSIC)

NRC Resident Inspector State of New York OFFICIAL RECORD COPY

~ 0

~ ~

~ ~

AUG 8 4 19)7 bcc w/encl:

Region I Docket Room (with concurrences)

Nanagement Assistant, DRHA (w/o encl)

DRP Section Chief Robert J.

Bores, DRSS RI: ORSON Tuc 'nardi 8 p/87 SS Laza us 8/i /87

,V Bellamy 8/

/87 OFFICIAL RECORD COPY

~ ~

~ ~

~ ~

NINE MILE UNIT 2 EMERGENCY EXERCISE REVIEW COMMENTS AUGUST 26, 1987 1.

Release rate (pCi/sec values for the stack effluent monitors, particulate iodine and noble gas concentrations, and stack flow rates were omitted from the process rad monitor data in Section 8. 1.

2.

The status of emergency condensers (ll/12) was omitted on the plant parameters and equipment status sheets (Section 8.3).

3.

Onsite whole body dose rate values were omitted from Section 9.3.

4.

There appears to be a discrepancy between reactor building vent monitors.

The CAM is O.S.H.

from 1100 to 1230 while channels 11 and 12 of the vent monitor remain constant throughout the exercise at

1. 1 and 1.6 mR/hr.

5.

-Supplemental scenario 81 implies that the controller will ensure the repair team is evacuated from the reactor building (elevation 237

)

before fuel damage occurs.

Evacuation should be initiated by the players in anticipation of fuel failure.

6.

Plant status, Message No. 28.

The time is incorrect.

It should be 1230 instead of 1215.

~ ~