ML20148G953

From kanterella
Jump to navigation Jump to search
Discusses Three Visits to Facilities on 780118 Re Environ Qualification of Class 1E Equipment
ML20148G953
Person / Time
Site: Millstone, Haddam Neck, Yankee Rowe
Issue date: 02/10/1978
From: Anderson N
Office of Nuclear Reactor Regulation
To: Ziemann D
Office of Nuclear Reactor Regulation
References
NUDOCS 8011140375
Download: ML20148G953 (3)


Text

F a, ,

f

":a;:

r DocketHk 50-213/50-245 .

1 FEB 101978 l p

MEMORANDUM FOR: Dennis L. Zienann, Group Leader, Systematic Evaluation Program Review Group, DOR FROM: Newton R. Anderson, Systematic Evaluation Program 7 Review Group. D0R ).

SUBJECT:

REPORT OF VISITS TO YANKEE ROWE, MILLSTONE 1 AND l HADDAM NECK FOR DISCUSSIONS ON ENVIRONMENTAL j

~~

QUALIFICATION OF CLASS 1E ELECTRICAL EQUIPMENT This report covers three trips made by Newton Anderson, Daniel Mcdonald, ., p b

and Philip DiBenedetto to Yankee Rowe, Millstone 1 and Haddam Neck is Huclear Power Plants for furtber discussions on the environmental is qualification of Class 1E electrical equipment. g3

}::

Discussions with the two utilities, Yankee Atomic Electric Company n (YAEC) for Yankee Rowe and Northeast Utilities Service Company (NUSCo) [.:

for Millstone 1 and Haddam Neck, were concluded prior to touring the P

, plants. The purpose of the environmental qualification review and

  • the plant visits was explained. The Systematic Evaluation Program, SEP, was discussed in general and the relationship between the specific topic of environmental qualification of electrical equipment and the SEP was specifically explained. The licensees were given guidance with regard to the contents of their responses to the NRC letter of December 23, 197E. The staff emphasized that responses to the December 23 letter should: (1) include a comparir,on of the existing <

environmental qualification of safety-related electrical equipment with current requirement as specified in IEEE 323-1974 and Regulatory Guide 1.89 and (2) address other design basis euents such as steam .

line break accidents, high energy line breaks outside containment -

and loading of equipment as well as the limiting loss of coolant pj accident. -

1 j

Following the discussions the plants were toured for the purpose of observing the location and configuration of plant safety-related Ll equipment. Each plant is discussed separately below. "

/

THIS DOCUMENT CONTAWS POOR QUAUH P 9 L -

s'o n 1 4 0 N F O

5

  • f 7

, , ~

Dennis L. Ziemann FEB 101978 Yankee Rowe 9_ ' ']

YAEC has three people assigned to the SEP program, Jim Stacey, E Dave Hansen and Jim Martin. They had already started collecting F ~

information and had selected a femat for presenting the data which is in close agreement with the requirements developed by the SEP Group. The main steam line break is not a major problem at Yankee Rowe because only a limited amount of safety-related equipment is inside containnent. There were no problem areas ,

identified during the plant tour. Bill Lazarus, T&E principal '

inspector, and Stuart Ebnetter, I&E Region I Electrit.a1 and :a Instrumentat6nn Supervisor, and A11Schwencer DDR Projects .l Branch Chief, accompanied the SEP Team on the plant tour. ~

Millstone 1 b[.

[

g W A team of the SEP Group accompanied by Dennis Ziemann, SEP Group G ,

Leader, and John T. Shedlosky, I&E principal inspector, toured p the Millstone plant on January 18, 1978. We did not go into the si containment at M119 tone. The off-gas system was being modified F

~

and radiation levels in the containment were higher than normal.

The modifications for protection of high energy breaks outside containment were observed. No specific problem areas were noted.

~

Haddam Neck Mr. Bill Lazarus, I&E principal insi>ector, accompanied the SEP team on the tour of the Haddam Heck facility. We entered the -

containment to observe the location of the unprotected terminal i boards which are used for cable connections at the electrical L I-penetrations. They are located opposite tho main steam line penetrations and are protected fron direct impingement of steam. .

Several piping system are located in the vicinity and all were identified for us. Touring the remainder of the facility revealed no obvious problem areas. .

.,; f N CLU % $ 0?g/mbq F

Newton R. Anderson Systemtic Evaluation Program f' .'

Rev.iew Group Division of Operating Reactors  !

o,rtC

D()R:SEP auRN.-* A nderson.Lah . 0LZienann._..

,, 2//6 /78 2/p/73 l NRC IORM 318 (9-76) NRCM 0240 W u: s. oOV.RNM NT PRINTING OF FIC es 1974 - S$6 814

I g .

q -

. o DISTRIBUTIO_N_

~

Docket File NRC PDR Local PDR NRR Reading E. Case V. Stello :u D. Eisenhut :q K. Goller #

R. Baer i W. Butler B. Grimes

, L. Shao .

A. Schwencer  ! J D. Davis :l G. Lear . . .i R. Reid -R SEP Reading file R. Devan _

OELD r R. F. Fraley, ACES (16)

) I&E(3)

T. Abernathy J. Buchanan N. Anderson i D. Mcdonald P. DiSenedetto -

e