ML20077G583

Third & Final Set of Interrogatories.Related Correspondence

ML20077G583
Person / Time
Site:	Limerick
Issue date:	08/01/1983
From:	Lewis M LEWIS, M.
To:	NRC OFFICE OF THE EXECUTIVE LEGAL DIRECTOR (OELD), PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
References
NUDOCS 8308040341
Download: ML20077G583 (3)

Text

& #

UNITED STATS OF AMERICA

• n be*,s

. . NUCLEAR REGUIATORY COMMISSION llSNg REIATED CCDUESPOYDFNCN $g ,

PHIIADELPHIA r"LECIRIC C0 Dockets Nos. 50-352 and 50-353 gu,y e

(Limerick Generating Station Units 1 and 2) x- ,.

\'-

_INTERVENCR I24IS *S THIRD AND FINAL 3ET OF INTERROGATORIES TO THE NRC STAFF AND LICENSEE.

In conplianca >:ith the M and 0 of May 16 ,1983, Intervenor Lewis submits his third and final set of interrogatories to the NRC staff and the Licensee. The reason that this sat is being filed on the very last day is that "new" information on Hias was recently issued from the NRC. I have subsequently awaited and requested clarification of the "new " information . Such clarification could possibly have eliminated at least one of the following interrogatories. I waited as long as I could without loosing my right to question.

The previous " definitions and instructions" used in Intervenor's Second Round of Interrogatories will also apply to the following set of interrogatories.

I have appreciated the NRC staff and the Licensee's efforts to completely and accurately answer the Intervenor's interrogatories which were not drafted to exacting legal standards and hope that they sill continue their cooperation. The answers to date appear truthful, pointed and complete as possible. I hope that the Staff and Licensee will submit any further information concerning my previous interrogatories as it becomes available.

1. For the NRC Staff:

In the "NRC Response to the first set of interrogatories on contention I-62" , the staff states,"t eh basic conditions under which EWas operate make it much less likely for F4Rs than for Pias that the simultaneous rapid cooling and high pressure necessary to create a FIS will occur."

The response leaves open the question,"Are there any set of conditions wherein a F4R can experience the simultaneous rapid cooling and high pressure necessary to create a significant PIS?"

Further, can a NR experience a cooling (rapid or not) which will produce significance stresses at temperatures close to RTndt in any temperature -pressure boundary?

l Please answer above two questions regarding any set of conditions that can produce a PTS in a 34R.

Also refer to NRC Memorandum UNANALYZED REACTOR VESEL THERMAL STRES DURING COOLDOWN l from Eisenhut for Commissioners dated April 12, 1983 Discuss whether this type of

! stratification could occur in a PWR and its effect upon thermal stresses. Include in l your discussion any staff concerns on the operability of safety relbf valves which could l complicate the thermal picture. Also discuss how natural circulation can fail or be reduced.

l Document request related to above interrogatory. Please provide GE NEEE 24988 P,

" Analysis of Generic BWR Safety Relief Valve Operability Test Results." I do not know the date nor availability as I have only read a short synopsis, hG D,' .. l. E ' "

~*h0 % N V -

.&& .A-f

2.

l For the Licensee: Please answer the two questions in Interrogatory 1. You need not refer to the NRC or the GE docunent in in anwer. Please refer to subscript a of your answer to Interrogatory No. .2 AT page 3 your. Discovery 8 June 13,1983

2. Documents request: To the Licensee: In discovery 8 ,yuu refer to several documents given out as pmviously provided as Discovery 2 , Enclosure 3, Iten1.

and 2,3,13 and 2,3,5 Can you give the date and title of the cover letter. I can not )

find them. Please check if they were sent to me. I may not be checking back far enough. l

3. To both the Licensee and staff:Recently the NRC releases an order concerning the ongoing IGSCC in NRs. I have attempted to get further information on this without success.

Therefore , I am submitting the following interrogatory on the relationship of IGSCC to PTS in W Rs.

Are any structures which receive neutron irradiation subject to IGSCC? discuss the feedwater nozzle and piping as mentioned on page 5 3-7 of the ICS FSAR , Para. 5.3.15 3

a. Has all "new" information on unresolydd safety issues been factored into the FIS -

problem as the information has become available?

b. Have all synergistic or cumulative effects from other WI been factored into the PTSproblem and its consideration by the Licensee and NRC staff? Give specific examples.

Discuss W I of " cold overpressurization"in your answer.

c. Are there any other concerns not comered in the WI which can or do have an effect on the consideration of PTS been considered adequately at IGS7 Discuss measurement of neutron flux ( PEco Boyer to Eisenhut April 15,1983, Page 4, last passgra.ph) and difficulties of ultrasonic testing (NRC Schwencer to PEco Bauer , June 3,1983, MIB enclosure Itge 250-8 'aragraph 250.4 ani 250.3 .A.)

4 To the NRC staff: In the NRC Staff Response to Intervenor iewis's First Ste set of Interrogatories in PTS Contention (I-62.), the staff states,"ibor WRs /4 plants including Limerick , tre location of fluiti systems in;)ection d4es not result in direct impingement on the vessel wall." Page 3

• dhat does fluid sys'em impinge directly upon? Are any of these structures able to fail in a PIS situation or during a transient? Are any of these structures made of amaterial which will change RTndt with neutron flux?

Also provide a drawing of a jet pump and a description of its function and material of construction.

5. To the staff : Document request: Please provide GE NEDO 10029, An Ana&ytical study of Brittle Fracture of GE WR Vessels subject to a Design Basis Accident."

a. How were assumptions in above study selected and how were they deter:ined to be

" conservative."

b. "efine " conservative."

6. To licensee: See IGS FSAR Figure 4.3-29 Is the shroud shoun in Figure 4.3-29 continuous? Are there areas where the vessel wall is not shrouded from the core? Specify all such areas. Specify neutron flux for unshrouded areas.

I 9 , ' . sd ' * .

-%$ OR,0*r -

ero - a ..

3 l

7. To the licensee and staff In my Interrogatory 6 of my first set of Interrogatories ,

I was looking for an yes c no answer. Please provide an yes or no answer to 1 the following repeat interrogatory.

l Have any " test coupons" of affected materials been irradiated'and tested from BWRs of design similar to Limerick?

a. To the staff: Reference E-7 has not yet been published. I therefore cannot make a document request. Hopefully you can provide soms information noneheless. Please provide the number of Charpy test whcih were used to determine the Guthrie trend curve, standard deviation, and 2 sigma upper bound. .

If possible , provide the statistical value of " confidence " for' the above data. Provide the reference from whch the statistical values were devel.oped...

I am mailing this set of interrogatories out to the entire Docket 50-352 and 50-353 IGS units 1 and 2 today , August 1,1983 , by first class mail , myself._

p W-

. Respectfully submitted, _.

/ /

n / /

. . .-.- , - i e

M. t. L E w h WY . *' *

% :-z x. ..

- D G l

e e.

- - -- v~