ML20213F170

From kanterella
Jump to navigation Jump to search
Forwards Sser Input in Response to H Schierling Request Re NUREG-0737,Items III.A.1.2 & III.A.2.2. Re Upgrade of Emergency Support Facilities & Meteorological Data, Respectively.Items Completed Satisfactorily
ML20213F170
Person / Time
Site: Diablo Canyon, 05000000
Issue date: 04/22/1985
From: Matthews D
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
To: Knighton G
Office of Nuclear Reactor Regulation
Shared Package
ML20213E738 List:
References
FOIA-86-197, RTR-NUREG-0737, RTR-NUREG-737, TASK-2.B.2, TASK-3.A.1.2, TASK-3.A.2.1, TASK-3.A.2.2, TASK-TM NUDOCS 8504300636
Download: ML20213F170 (6)


Text

,.-. .. n.u - .- . - - - - - - . . . - .. - .-- - . - _

N i. .

  • lL q vPlio .

fl . 4 UNITED STATES .

f p, NUCLEAR REGULATORY COMMISSION.

WASHINGTON, D. C. 20655 E j

% . , , , . * 'g April 22,1985 MEMORANDUM FOR: . George W. Knighton, Chief j: Licensing Branch No. 3 Division of Licensing-Office of Nuclear Reactor Regulation FROM: David B. Matthews, Acting Chief Emergency Preparedness Branch-Division of Emergency Preparedness and Engineering Response _

Office of Inspection and Enforcement-

SUBJECT:

DIABLO CANYON 2 SSER INPUT ON SELECTED NUREG-0737 ITEMS q The enclosed infonnation is in response to a request from H. Schierling,

Project Manager, on input to the Diablo Canyon 2 SSER on selected NUREG-0737 items. Enclosure 1 is a marked-up copy of a draft of Item III.A.1.2 provided by the PM. Enclosure 2 is a writeup of Item III.A.2. We find that these two
items have been satisfactorily completed by the licensee. This information was

{ given in advance to the PM on April 18 and 19,1985.

I

)' t

[ l 4

David B. Matthews, Acting Chief Emergency Preparedness Branch 1 Division of Emergency Preparedness )

, and Engineering Response  !

Office of Inspection and Enforcement l l

Enclosures:

1. Draft of Item III. A.1.2
2. Item III.A.2 i cc: see page 2 h '

I f

/

\

(. -

i 1 .

George W. Knighton *

.i T

1 l cc w/ cover memo only:

i- J. M. Taylor, IE

{ R. H. Vollmer, IE B. K. Grimes, IE J. G. Partlow, IE 2_ E. L. Jordan, IE

S. A. Schwartz, IE K. E. Perkins, IE D. B. Matthews, IE C. R. Van Niel, IE cc w/ enclosures:

j- F. Kantor, IE

H. E. Schierling, NRR i-4 4

e i

i 4

i i

i-A 1 -

i, i

i j

i 4

l l

i i

~ . - . .-. . . .. . . - . - .-. . - .

me.y,ye- ,g w m-t--v9 9 9 y -

-v y-r -J 3- Ts'4 yv vrew- , + - ,.wp- +cy'vy-yva-v- 4.- . -,-e-,9r- - + - e-y-w+--

G 'f f r (G~

~

4.14.2 ENCLOSURE 1 Safety Parameter Display Selection LATER 4.15 Uccrade of Emeroency Succort Facilities (Item III A I 2) . ..

The staff reported on the PG&E upgrade of emergency support f 1931 in SSER 14 for Unit I and Unit 2. acilities in April Sep ember 1981 in the Unit i low power license regarding

5e I:hedule # -

tesi fa: t'e: E.

+ :s erim facilities and e:aested a revis'. :3 -d Fe::e cer 20, 1952 OGLE c' : e E-i; ' s: hec.'.e en :ne cast s of f

'NRC guidance (Ref. 97). In Decemb(.

cc:hccming fur:ner GL 82-33, Supplement 1 to NUREG-0737, " Require =ents Cacability" (Ref. 42). ergency Response numoer of NUREG-0737 items, including Faci'. ft skt; III. A.1.2 mergency Support Parameter Display Console.I.D.1 - Control Room Design Revie in GL 82-33 by letters dated April 18 and Septemcer 19 (Ref

89. 90 and 91). ,1983 and Acril 30, 1980 03&E also proviced specific informati contrcl ecem design revien-on regarding the C

ec 'at0*v Gu'de 1.97 Tnese

. (CRDR). safety parameter display system, (SPOS) and tub.ie:t!

rescrt.

In havemcar 19S4 are addressed in detail elsewhere in this

'incluced as a license condition the PGLE schedule in n .,nich citting the CRDR report by December 1984, (2) ccmpletion of e 91 for (1) on the SPDS and emergency operating procedures (EOPs) by Ma cperat rch 28, 1955, and (3) inclementation of the EOPs, based er the Westingh ines, also by March 25 . 1955. ouse Owners Group guide-

? " '.E . N l e: t e - da ;. ' Dec e ..w !

.a  ::

I??.; ( Le i . c?i,

! crd U" t 2 aro L/ 9: . - On t .- d ~ s i .2 w-- ' t:+d the CRDR reme:

1

, 19:5 (Ref 93) stated that modifications implementec fcc Unit 1 had als as aorropriate.

This W , fulfills the require.ents of the Unit I licenso bee 6.d no such condit4cnp A required for Unit 2 .

e condition 02 0 . i5 ,

4-19 01AE.LO C1'WO'. 55Eh .;l SE :

t -

PG&E provided further information on th operator training in a letter dated March 26, 1985, stating that the operator training on the SPOS and the E0Ps has been completed for Unit I and Unit 2 (Ref. 98). This fulfills the require-ments of the second element af the Unit 1 full power license condition on emer-gency response capabilities and no such condition is required for the Unit 2 license.

PG&E provided information on the . implementation o ' upgraded emergency operating procedures for Unit I and Unit 2 in a letter dated February 27, 1985 (Ref. 99),

and by letter dated March 26, 1955 informed the staff that the E0Ps have been implemented for Unit I and Unit 2 in accordance with the Westinghouse Owners Group guidelines (Ref. 98).

This fulfills the third element of the Unit 1 full ec,wer license cendition aad no sucn crndition is recuired fer the Unit 2 license.

Q The Technical Support Center (750) and Emergency Operations Facility (EOF) -

serve both Unit I and Unit 2. By letter dated February 28, 1985 PG&E stated thatbothfacilitiesareoperational(Ref.102)]

4 The staff has reviewed the information provided by PG&E with respect to the upgrade of che e=ergency support facilities in accordance with the guidance of NUREG-073', Supplement 1.

The staff concludes that the requirements .in the Unit 1 license condition have been met and no e utvalent condition -be,wrecuired for tne Unit 2 license. ThestaffwillcoIcact 4 appraisa of the ~

ccm;:leted Diablo Canyon emergency resconse facilities to verify that the require-ments cf HUREG-0737 Sucolement I have been satisfied,aad the tht- the-Te.Oi-wn:- -e f ,.c i M. : ,;, tF c k . c.e A e t f urnka . '

4.16 Plant Shieldino (Item II.B.2)

In SSER 14 (April 1981) the staff reported on its evaluation of the PG&E Diablo Ca ycn Ur.it I radiation shielding review. "

The staff identified the need for additional-information regarding pre.iected post accident dose rates for occapied a-eas. D T e"t hily r.w.ai rd a rea s and t a ve l r wt e s .

These were te he s # "t'ad

m
:. the i;suance c.f a f,11 p .ter !!cena .

by pG&E on June furti.: info matice was i.rcvide 12,1951 (Ref.100) and the Unit I low power license was issued in September 1951.

By letter July 12, 1964 PG&E submitted " Radiation Shielding 01'O55  ;-;?

OIAELG CMa0N S5EP 31 3EC 4

! I. . ,

ENCLOSURE 2 III.A.2 Improving Licensee Emergency Preparedness-Long Term III. A.2.1 Upgrade of Emergency Plans The objective of this requirement is for each nuclear facility licensee to upgrade its emergency plans and preparedness to provide reasonable assurance that adequate protective measures can an6 will be taken in the event of a radiolog-ical emergency. The licensee has submitted upgraded emergency response plans and procedures for the Diablo Canyon facility in conformance with the final regulations on emergency planning and the guidance criteria of NUREG-0654/

FEMA-REP-1, Revision 1, dated November 1980. In addition, upgraded radiologi-cal emergency plans for local and State jurisdictions within the 10-mile and

~

50-mile Emergency Planning Zones for the Diablo Canyon facility have also been submitted. The onsite plans and procedures have been reviewed by the NRC while the offsite plans have been evaluated by FEMA. In addition, the NRC has conducted onsite appraisals of the emergency program at Diablo Canyon and both the NRC and FEMA have observed the exercises conducted to date at the facility.

This review effort has resulted in a finding by the NRC that the state of onsite and offsite emergency preparedness provides reasonable assurance that adequate protective measures can and will be taken in the event of a radiolog-ical emergency at Diablo Canyon. The staff considers this item satir.factorily completed.

1 e

e

5*.

J III.A.2.2 Meteorological Data Requirements under this item have been superseded by the requirements in Supplement I to NUREG-0737, dated January 1983. In essence, Supplement I requires reliable indication of meteorological variables specified in RG 1.97, reliable indication of meteorological conditions in the vicinity (up to about 10 miles) of the plant site, and information on meteorological conditions for the region in which the site is located via communication with the National Weather Service. The meteorological program for emergency response for the Diablo Canyon facility has been evaluated by the staff during the course of the emergency plan review and the onsite emergency plan implementation appraisal.

The staff has found the licensee's meteorological program to be acceptable.

The meteorological program will be further evaluated by the staff in a post-licensing appraisal of the adequacy of the Diablo Canyon emergency re-sponse facilities in accordance with the requirements of Supplement 1 to NUREG-0737. This appraisal is currently scheduled for June 1985.

. - - - -- - . . - - - . . - -