ML17275B013

Forwards Safety Concerns Associated W/Pipe Break in BWR Scram Sys. Requests Evaluation & Analyses of Rept Applicability to Plant,As Well as Appropriate Remedial Measures

ML17275B013
Person / Time
Site:	Columbia
Issue date:	04/24/1981
From:	Tedesco R Office of Nuclear Reactor Regulation
To:	Ferguson R WASHINGTON PUBLIC POWER SUPPLY SYSTEM
References
NUDOCS 8105040008
Download: ML17275B013 (4)

Text

C:,

Dist, LDocke.t-Fi-le~

LBb'1 Rdg DEisenhut BJYoungblood bcc:

TERA DLynch NRC/PDR MRushbrook L/PDR RTedesco NSIC RVol lmer TIC TMurley CRS (16)

DRoss RHartfield,-

VNoonan p

4P

//~

OELD g/,

/I/

OIE (3)

+

jgg 81~

ram APR 24 ISS)

Docket No.:

50.-397m Washington Public Power Supply System ATTN:

Mr. R. L. Ferguson Managing Director 3000 George Washington Way Post Office Box 968 Richland, Washington 99352

Subject:

Safety Concerns Associated with Pipe Breaks in the System On April 9, 1981, we discussed with your representatives the NRC's Office of Analysis and Evaluation of Operational Data (AEOD) report entitled, "Safety Concerns Associated with Pipe Break in the BHR Scram System."

The Report describes a potential sequence of'vents which could result from a break in the BWR scram discharge piping during a scram condition concurrent with an inability to reclose the scram outlet valves.

Concerns identified include the quality of the scram discharge volume piping, the ability to detect and isolate such a break, and potential water and steam degradation of available ECCS equipment as a result of the break.

A number of recommendations were made in the report to remedy the potential concerns.

We are presently studying these issues and recommendations to determine whether the BWR design basis accidents should be modified and as a consequence whether appropriate actions should be taken for operating BWR plants.

The purpose of this letter is to provide to you the AEOD report so that you can evaluate its applicability to your plant and determine appropriate remedial

measures, and to request information from you concerning your evaluation in order to assist in determining an appropriate course of action for the NRC.

Therefore, please provide us within 45 days of your receipt of this letter, the following information:

1.

A generic evaluation of the applicability of the indicated sequences of events in the REPORT to the BWR plant

design, your estimate of the probability of occurrence of such sequences, and the bases for these conclusions, 2.

A generic evaluation of the applicability of the indicated safety concerns and findings in the REPORT relative to BWR plant construction,

design, and operation and the bases for these conclusions, and 0

0FF1Cfg SURNAMfg 0ATfP NRC FORM 318 RO/80) NRCM 0240

~ ~ ~ ~ ~ ~ ~ ~ ~

~ ~ ~ ~

~

~ ~ ~ ~ ~ ~

~ ~ ~ ~ i ~ ~ ~ ~ ~ ~ 0 0

~

OaFFICIAL RECORD COPY

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

A USGPO> 1980-329 824 1

4 PJ'S

/

a V

/I'I

'l h ~

H tl lr

43 R. L. Ferguson 2

3 ~

A generic evaluation of the recommendations listed in the REPORT discussing the, degree to which the recommendations are being or. have been implemented with bases why the recommendations should or should not be completely implemented on BNs.

In addition, provide the following information within 120 days of your receipt of this letter:

2 ~

3 ~

Provide an evaluation of the applicability of the 45 day generic evaluation to your plant. This evaluation should contain plant specific considerations related to system design, instrumentation, construction, operation, operator

training, and emergency procedures for your plant.

In light of the AEOD report and the 45 day generic evaluation, provide a plant specific evaluation of your facility's Scram Discharge Volume System conformance to GDC 14, GDC 35, GDC 55, 550.2(v), 50.55a (including footnote 2),

and 550.46 of the Commission's regulations.

This evaluation should address which portions of the Scram Discharge Volume System are considered to be part of the reactor coolant pressure

boundary, the quality group and safety class of the Scram Discharge Volume System, the codes and standards used for the design, fabrication and inservice inspection of this system, and your bases for the above classifications or groupings.

Provide by analysis or reference a demonstration that a break in the Scram Discharge Volume System meets the requirements of 550.46 of the Commission's regulations, taking into account the environ-mental and flooding aspects of such a break It is our position that this item must be resolved prior to issuance of an operating license.

Sincer ely, Original se4 by f?0bert L. Tedesco Robert L. Tedesco, Assistant Director for Licensing

Enclosure:

As stated cc:

See next pag w/enclosure OFF I SURNA y

aaTEf>

4/If/81

~ ~ ~ ~

0 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

4/

100d 81 0 ~ ~

~

RLTedegco 4/AO/81

~ ~ ~ ~ ~ t

~

~ I ~ ~ ~ ~

~ ~ ~

~ ~ ~

NRC.FORM 3IS IIO/801 NRCM 0240 OFFICIAL RECORD COPY

• USGPO: 198~29.82y

k

<CJ 63r4,4.'~ Ilil5IQ~Q

~oeob>T.J mac.'.~-".*