ML20236V396

From kanterella
Jump to navigation Jump to search
Forwards Discussion of Inconsistencies Noted in Aug 1987 Rev 20 to Plant Radiation Emergency Plan,Per Guidance in NUREG-0654,App 1 & Attachment 1 of Info Notice 83-28. Corrections Requested within 45 Days of Ltr Date
ML20236V396
Person / Time
Site: Summer South Carolina Electric & Gas Company icon.png
Issue date: 11/27/1987
From: Dan Collins
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To: Nauman D
SOUTH CAROLINA ELECTRIC & GAS CO.
References
RTR-NUREG-0654, RTR-NUREG-654 IEIN-83-28, NUDOCS 8712040275
Download: ML20236V396 (3)


Text

GLwth i

NOV 2 71987 South Carolina Electric and Gas Company ATTN: Mr. D. A. Nauman, Vice President Nuclear Operations

.P. O. Box 764 (167)

Columbia, SC 29218 Gentlemen:

SUBJECT:

V. C. SUMMER EMERGENCY PLAN REVIEW, REVISION 20 DOCKET NO. 50-395

-We have completed our-review of changes incorporated as Revision 20 to your V. C. Summer Radiation Emergency Plan, dated August 1987.

Our review indicates that two of the changes are inconsistent with the guidance in NUREG-0654, Appendix 1, and Attachment 1 of Information Notice 83-28,

" Criteria for Protective Action Recommendations for General Emergencies."

Please' note the Enclosure to this letter which includes those items.

We acknowledge the appropriateness of the actions that were taken in response to our review of changes incorporated as Revision 18 to your Plan (specifically, Item 4 of the Enclosure to our letter, dated February 11,1987)..You should not continue to implement the changes discussed in the referenced enclosure.without providing supportive justification.

Please modify the appropriate pages of your Plan, or provide to this office justification and documentation to support such changes.

We request that these corrections or justifications, including an evaluation to support changes, be provided to us within 45 days of the date of this letter.

Our review of the remainder of the changes incorporated as Revision 20 to the:

Summer Plan meet the provisions of 10 CFR 50.47(b), 10 CFR 50, Appendix E, and criteria in NUREG-0654, Appendix 1.

Please be reminded that 10 CFR 50.54(q) requires that proposed changes which decrease the effectiveness of your Emergency Plan.shall not be ' implemented without application to and approval by the Commission.

However, changes may be made without Commission approval if such changes do not decrease the effectiveness of the Plan, and if the Plan, as changed, continues to meet the standards of 50.47(b) and the requirements of Appendix E to 10 CFR 50.

If a change is made without approval, you should furnish copies in accordance with 10 CFR 50.54(q).

Additionally, any changes to the Emergency Plan Implementing Procedures should be made in accordance with the requirements of 10 CFR 50, Appendix E, Section V.

8712040275 871127 PDR ADOCK 05000395 F

PDR PW

South Carolina Electric and Gas Company 2

Should you have any questions or dir.cussions regarding this letter, please contact Mr. Thomas R. Decker of our staff at (404) 331-2559.

Sincerely, ORIGINAL SIGNED BY DOUGLAS M. COI.UNS Douglas M. Collins, Chief Emergency Preparedness and Radiological Protection Branch Division of Radiation Safety and Safeguards

Enclosure:

Inconsistencies in Plan cc w/ encl:

0. S. Bradham, Director, Nuclear Plant Operations J. L. Skolds, Deputy Director Operations and Maintenance J. B. Knotts, Jr.

Debevoise and Liberman W. A. Williams, Jr., Special Assistant, Nuclear Operations -

Santee Cooper A. M. Paglia, Jr., Manager Nuclear Licensing l

bcc w/ encl:

NRC Resident Inspector J. Hopkins, Project Manager, NRR Document Control Desk I

RI RII RI b

H"J

/ "'* :

" " 4-***

Cc"'c " re " cc-

,,g O

D A M D'"*

i AGooden TDec r HDance 11/20/87 11/p/87 likt/87 db 157

?cv' P c w C(>>vc<n44c'd h

wi r tac m c a e,. m upop1.

a 1

i A

E_NCLOSURE Inconsistencies in Plan I

i 1.

In Section 4.1, Table 4-1, Item 11, Page 32 of Revision 20, the initiating condition for Site Area Emergency, states,. in part, that most or all annunciators lost for more than 15 minutes and plant transient initiated or in progress.

The time allowance of more than 15 minutes, is inconsistent with Item 12, Page 1-13 of Appendix 1 to NUREG-0654.

The cited time allowance for declaration of the event could result in l

undetermined conditions which raay compromise plant safety.

2.

Table 6-3:

The General Emergency Protective Action Recommendations Flow Chart does not consider a core melt sequence where significant releases from containment are not yet taking place and large amounts of fission produm are not yet in the containment atmosphere.

This finding is inconsistent with Item 4, Page 1-17 of Appendix 1, to NUREG-0654, and Attachment I to Information Notice 83-28.

l.

a I

]

b