ML20129F948

From kanterella
Jump to navigation Jump to search
Forwards Memos Re Determination of Licensee Response to Westinghouse Ltr on Postulated Fuel Handling Accident Analysis,Per Request of Technical Instruction Ti 2500/1
ML20129F948
Person / Time
Site: Wolf Creek, South Texas, Comanche Peak, 05000000
Issue date: 07/14/1977
From: Seidle W
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To: Jordan E
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
Shared Package
ML17198A238 List: ... further results
References
FOIA-84-393 NUDOCS 8506070090
Download: ML20129F948 (1)


Text

-.

s.

4.

July 14,1977 i

MENOPANDUM FOR:

E. L. Jordan, Executive Officer for Operations Support j

(X005)

FROM:

W. C. Seidle, Chief, Reactor Construction and Engineering Support Branch, RIV

SUBJECT:

DETERMINATION OF LICENSEE RESPONSE TO THE LETTER FROM l

WESTINGHOUSE CONCERNING POSTULATED FUEL HANDLING ACCIDETE b

ANALYSIS (TI 2500/1,5/4/77) i j

In accordance with.the request of TI 2500/1, the enclosed memoranda are i

forwarded. The memoranda comprise responses covering Wolf Creek, Unit 1 (Kansas Gas 1 Electric Company), South Texas Project, Units 1 & 2 (Houston

_ Lighting & Power Conpany) and Comanche Peak, Units 1 & 2 (Texas Utilities Generating Company). These three facilities are the only ones in RIV J

having a CP for which Westinghouse is NSSS. The answers to the questions in the TI have been given identical numbers in the enclosed responses.

t l

If you have any questions concerning these responses, please contact me.

f cwfaJ sped by W. A. c.mmen

em W. C. Seidle, Chitf Reactor Construction and Engineering Support Branch

Enclosures:

1.

Response for Wolf Creek, Unit 1

/

l 2.

Response for South Texas Project, Units 1 & 2 3.

Response for Comanche Peak, Units -1 & 2

- - ~ ~ ~...

6 e. ;

, t' M

8506070090 840620

'L

., f-.'L-hFOIA194-393 PDR

)

l RIV r g W'

WC e,,.. e,

Crossman

/,A.elq1e

/pberg/nh

...s#

7/ 14/ 77 7/14R7_.d 7414477_

Pape. TIC.its tRe*. 9 5 9) AsCM 0340

  1. w. s. eeves..e e mtmo e,, esse sota.ese.see

su.

X

/5 j

DockettNo.x50-498 Noves6er 14,1977 50-499 MEMORANDUM FOR:

N. C. Moseley, Director, Division of Reactor Construction. Inspect 1on 4

FROM:

W. C. Seidle, Chief, Reactor Construction and Engineering Support Branch, RIV

SUBJECT:

ASME SECTION III, DIVISION 2. APPENDIX VII (AITS F40291H1) j.$,.

Recently, difficulties have been experienced at South Texas Pro, ject 4

i (DN 50-498; 50-499) Mlative to the requimments of ASE B&PV Code, 9

Section III Division 2. Appendix VII, " Qualifications of Personnel.'

'l (t ;.~.

Thme specific problems have been encountered.

i i

' t(,i 1.

Article VII-4100 states in part, "When inspections and tests are implemented by teams or grows of personnel, the responsible pomon must participate and must meet the minianas qualification

' ].

l-<

\\

indicatad."

3 1

\\

N a.

What is meant by " participate" in VII-41007 Could the Y,

" responsible person" be seated in the vicinity of place-ment or out to lunch and still be considered as partici-h.'.

pating?

'p N.

4 b.

What are the qualification requirements of assbers of the group or team reformd to in VII-4100 if they are not a

" responsible person"7 Recommendation:

c' It is recanunended that the above quoted sentence be deleted from

! Article'VII-4100. This sould require that all concrete test and i

/ inspection inspectors be certified to the levels requimd by n' Article VII-4300.

6 f

/.

l t

l'! ! CONTACT:

R. G. Taylor, RIV

/

334 2411 h Y k T*) f k -f

/

i

~

RIV M d wM H61%h

/1Nid5 '

11/N/77 11NV/77 wac sonx na n.m wacx eue

  • w
  1. e w.ni=i a

.~.

n

~

se.

l M. C. Moseley ~

i 2.

Article VII-4300 under VII-4320(d) designates that inspection of concrete placement is a function of a Level II qualified person.

Likewise other Level II activities specified in VII-4320 could 1

readily be performed by Level I inspectors.

Recommendation:

Add the following itens from Article VII-4320 to the list of Level I capaht11 ties specified in Article VII-4310 with the qualifying

., j requirement that these activities be performed under the periodic f

surveillance of a Leeel II inspector:

Items b, c. d, e, f and g.

3.

Article YII-3300 places strong reliance on academic training in lieu of exper.ience and job-specific training.

Recommendations:

t I

a.

Develop relatively extensive written test requirenants sistlar j

to SNT-TC-1A for each level to provide reasonable standardi-i zation in the industry. The level of difficulty can then be i

reasonably assessed and controlled by an AI or by MRC. Testing for recertification then becomes practical sigly by changing examination contents, b.

Provide added capability to qualify personnel short on academic teaining or field esperience through job-specific training and testing as defined above.

c.

Provide guidance relative to on-the-job training of wider-qualified personnel including requirements for continuous and direct supervision by qualified personnel. Article j

VII-2210 should be qualified so it can not be misconstrued 1

l to permit use of trainees in lieu of qualified personnel.

J l

i i

i 9

I i.

l i

e f

Lo

~,

,,w k

.I 14 NOV 1977 N. C. Moseley 3

It is suggested that the above items be referred to the ASME for inclusion in subsequent addenda; but that in the interim, the NRC 6

interpretation of Article VII-4100 discussed in item 1 above be j

the subject of a Regulatory Guide.

" Original Signed b

/

B. E hALLu

.(c,,,

W. C. Seidle, Chief Reactor Construction and Engineering Support Branch I

cc:

W. A. Crossaan R. E. Hall i

R. G. Taylor RC&ES Branch File 4700 l

I i

6 O

4 0

i t

~,

---_...-,,-_.n.-e.-n,-

-_