ML20092B127
| ML20092B127 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek, Callaway, 05000000 |
| Issue date: | 04/06/1984 |
| From: | Glickman D HOUSE OF REP. |
| To: | Bilinsky V, Gilinsky V, Palladino N, Roberts T NRC COMMISSION (OCM) |
| Shared Package | |
| ML20092B120 | List: |
| References | |
| REF-PT21-84 NUDOCS 8406200066 | |
| Download: ML20092B127 (5) | |
Text
'
D N bCN' N Wasni=cto*. O C. '20S 15 A
2"'"'"'*'"'
F u:TH D'$TRICT-KANSAS' 1
(2021225-4216 Cowwirtaas.
U S Count Houss AGRICULTURE Box 40Moou 224 JUDICIARY 6
396 SCithCE AND TECHNOLOGY CONGRESS OF THE UNITED STATES
'2*"'**'"'
e.....-susw.- m.a" TRAmsPOefATIO4, Aviafs04 AND MAttalALs 201 Noaru Main HOUSE OF REPRESENTATIVES wenhimot (3181669-8011 Aow.arnavns Ass.,..,
WASHINGTON, D.C. 20515 April 6, 1984 scon rauwa Lao.sufive Diascios PAY 4tCE GAACLA DistmeCf ACMintsTheToA Chairman Nunzio J. Palladino Commissioner Victor Bilinsky Commissioner Thomas M. Roberts Commissioner James K. Asselstine Commissioner Frederick Bernthal Nuclear Regulatory Commission 1717 H Street, N.W.
Washington, D.C. 20555
Dear Commissioners:
I am writing to request infort.ation pertaining to the licensing of the Wolf Creek nuclear reactor in Burlington, Kansas.
I have learned from your April 4,1984, " Weekly Information Report--
Week Ending March 30, 1984" memorandum from T.A. Rehm to the Commissioners that the Bechtel Power Corporation has notified the NRC that certain cables at the Wolf Creek plant are apparently defective.
The internal memorandum states that the apparent design deficiency affects approximately 50 valves at both Wolf Creek and the Callaway reactor in Fulton, Missouri, as the two plants are of similar design.
So that I may consider the seriousness of this situation, I would appreciate your response to the following:
1.
What is the design, safety and quality assurance significance of the potentially defective cables 1 2.
Had this apparent design deficiency not been detected prior to licensing, what adverse consequences could have resulted?
3.
The April 4, 1984, recorar.dum states that valves in the following systems "are af fected" by the apparent design deficiency:
S/G blowdown, essential service water and containment monitor isolation systems.
Please explain the safety significance of these systems aid identify what adverse consequences could have resulted from one or more valve failures.
4.
Why was this apparent design deficiency not previously detected by either the licensceor the NRC?
5.
What action will the NRC take to remedy this apparent problem?
0406'200066 840605 PDR COMMS NRCC CORRESPONDENCE PDR 9
THIS STATIONERY PRINTED ON PAPER MADE WITW RICTCLt3 Ft8tR$
7 1
..h'"
}
Commissioners Nuclear Regulatory Commission
' April 6, 1984 Page 2 I would also like to be provided with all documents including, but not limited to, internal staf f memoranda, analyses, reports and correspondence with the Bechtel Power Corporation or the licensee.
On a related matter, recent news reports have stated that the Nuclear Regulatory Commission is conducting an investigation of allegations made by former workers at the Wolf Creek project about quality-control and documentation problems. An article appearing in the April 5, 1984, edition of the Wall Street Journal quotes agency of ficials as confirming that an inves tigation is underway.
I would like to be kept fully and currently informed of the Commission's activicies in this case and expect to receive a copy of the findings of this investigative effort as soon as it is complete.
Thank you, in advance, for your attention to these reque :s.
Wit best re ar'i, l
i O~
D Glickman MEMBER OF CONGRESS '
DG:sm cc: Congressman Harold Volkmer Michael Lennen, Chairman, Kansas Corporation Commission Congressman Morris Udall, Chairman Committee on the Interior k
y
.I ENCLOSURE 3
- SNUPPS Standardized Nuclear Unet
=
Power Plant Syrtem 5 Choke Cherry Road Rockville. Maryland 20850 (3011869 8010 May 10, 1984 SLNRC 84-079 -
FILE: 0491.10.2 SUBJ: Supplemental Sionificant Deficiency Report (50R 84-02): Field Run Cables for Solenoid Valves Mr. James G. Keppler
-e Regional Administrator, Region III U.S. Nuclear Regula' tory Commission t@::~
t i
.799 Roosevelt Road i.,
Glen Ellyn, Illinois 60137 ii.. '
p' i A GB4 y,j, 9
Mr. John T. Collins b.L-Regional Administrator, Region IV U.S. Nuclear Regulatory Commission
' Suite 1000, Parkway Central Plaza Arlington, Texas 76012 DocketNbs.STN50-482andSTN50-483 f
Reference:
SLNRC 84-065, dtd. 4/13/84: Final Significant Deficiency I
Report (SDR 84-02)
)
- i-Gentlemen
The reference letter provided a description of a generic deficiency relating to improperly rated field run cabling used to connect Valcor supplied solenoid valves in Class 1E and non-lE applications.
As indi-cated in the reference, design changes have 'been 1mplemented to replace the field run cabling with high temperature cabling qualified for the environment experienced in these solenoid valves.
Field rework to affect the prescribed changes is currently underway at each SNUPPS job-Site and will be completed within the time frame initially specified.
[
The reference letter report also indicated that other equipment would l
be examined for excessive heat rise at field termination locations and that a determination would be made whether deficiencies exist similar to l
those observed with the Valcor valve connections. The scope of the followup investigation included items of potential high heat rise such as diesel generator auxiliary equipment, hydrogen recombiners, selected pump motors, packaged air conditioning units, solenoid valves (other than Valcor) and certain electrically operated components and equipment fur-nished by the NSSS supplier.
As a result of this investigation, similar 1
deficiencies were identified for the following equipment:
7 ti-M
- A99tTh 05 14051O c2 @
PDR ADDCK 05000482 h()
I h
~ ~ ~ "
S PDR L
< SLNRC 84-079 Page Two
- 1) Taraet Rock Solenoids: A total of 20 Target Rock solenoids furnished unoer the NSSS scope of supply for use generically in safety-related systems have deficiencies similar to those described in the reference letter., Actions are presently underway to rework these units, re-placing ex'isting field cabling with qualified, high temperature wiring /
connectors.
All rework will be completed at each jobsite prior to the time that these valves are required for their operational modes.
- 2) ASCO Solenoids: Two (2) ASCO solenoid valves on each of 12 condenser
~
dump valves (nonsafety-related) have been identified as Nving under-rated cabling connections (105'C max vs. 90*C available).
The existing installation was reviewed for service at the higher; i.e.105*C (Max),
temperature and the conclusion reached that, as a minimum, continued service would be permissible at each SNUPPS plant up to the first refueling outage.
Cables for the solenoids will b'e replaced on a schedule commensurate with eacty plant's maintenance and operational requirements.
In addition, one (1) ASCO solenoid valve on each of two (2) nonsafet'y-related Control Room HVAC heating / cooling water control valves will also require rework at each SNUPPS plant.
Cables for these units will likewise be replaced on a schedule commensurate with each plant's maintenance and operational requirements.
This supplemental report closes out all items relating to the generic deficiency initially reported on behalf of the SNUPPS Utilities and should be considered the final report on this subject.
If you have any questions regarding this matter, please do not hesitate to contact the undersigned.
~
~
Very truly yours, j /
Y) e S.
Seiken QA Manager SJS/dck/5a5 cc:
D. F. Schnell UE G. L. Koester KGE D. T. McPhee KCPL W. S. Schun NRC/WC J. H. Neisler NRC/ CAL
'B. H. Little NRC/ CAL R. C. DeYoung NRC/IE: HQ J. E. Konklin NRC/IE: III Record 4
e emu.
[
..1..
j.
t-L-
L' 1.
- DISTRIBUTION:
(*w/ incoming)
(**0CA needs l' copy) #14323
~ Docket File
- STN 50-482/50-483 NRC PDR*
j EDO Control No. 14323 i
EDO Rdg.
W. Dircks E.. Case /H. Denton M. Rushbrook i
'P. O'Connor J. Holonich-LB#1 Rdg.
D. G. Eisenhut/ Marie OELD' Attorney T. M. Novak/ Peggy G. Edison
~
G. Cunningham-R. DeYoung V. Stello T. Rehm J. Roe PPAS
.T. Speis R. Mattson R. Vollmer H.~ Thompson B. Snyder SECY (1)
K.-Bowman, P-428 #14323-OCA**
e
\\
4 i
a,
I a
'Y l
r s
~
.-V'
+
{
-g i y.
k, f,,'
a" 4
,',. p
?
-U
/
~
a l.____
.m.
. __I' LEE _mm^m.. m_1_' _ a
e
=
[
~ D'AN'bb'CKMAN.
2*n Rav=uaa saa'a FOURTH DisTaicTrKANSAS 02 2 26 Couemfiens:
U.S. Couar Houss AGRICULTURE Box 403-Room 224 WH:MffA, KANSAS 67201 JUDICIAT y ScrENCE AND TECENOLOGY CONGRESS OF THE UNITED STATES
'2*"'"*"*"*
- ==^"'==""a" TRA8tsroRTATIom. AVIAflom AND mATEmm 201 NonTu MAIN i
HOUSE OF REPRESENTATIVES
""'*"'"' " "^"'^s 6 7 so i 1
MvRNE ROE (316)669-9011 AommisfaATws AssesTAnr WASHINGTON, D.C. 20515 April 6, 1984 scon ruuas Lae6stATws Danacion FATF5CK GARCIA distr;.'T ADuomstaATOR Chairman Nunzio J. Palladino Commissioner Victor Bilinsky Commissioner Thomas M. Roberts Cotamissioner James K. Asselstine Commissioner Frederick Bernthal Nuclear Regulatory Commission 1717 H Street, N.W.
Washington, D.C. 20555
Dear Commissioners:
I am writing to request information pertaining to the licensing of the Wolf Creek nuclear reactor in Burlington, Kansas.
I have learned from your April 4,1984, " Weekly Information Report--
Week Ending March 30, 1984" memorandum from T.A. Rehm to the Commissioners that the Bechtel Power Corporation has notified the NRC that certain cables at the Wolf Creek plant are apparently defective. The internal memorandum states that the apparent design deficiency affects approximately 50 valves at both Wolf Creek and 'the Callaway reactor in Fulton, Missouri, as the two plants are of similar design.
So that I may consider the seriousness of this situation, I would appreciate your response to the following:
1.
What is the design, safety and quality assurance significance of the potentially defective cables?
2.
Had this apparent design deficiency not been detected prior to licensing, what adverse consequences could have resulted?
3.
The April 4, 1984, memorandum states that valves in the following systems "are affected" by the apparent design
. deficiency: S/G blowdown, essential service water and containment monitor isolation systems. Please explain the safety sip,nificence of these systems and identify what adverse consequences could have resulted from one or more valve failures.
4.
Why was this apparent design deficiency not previously detected by either the licensceor 'the NRC?
5.
What action will the NRC take to remedy this apparent problem?
THIS STATIONERY PRWTED ON PAPER MADE WITH RECYCLED F18Er.S
_')
^
a Commissioners Nuclear Regulatory Commission April 6, 1984 Page 2 I would also like to be provided with all documents including, but not limited to, internal staff memoranda, analyses, reports and correspondence with the Bechtel Power Corporation or the licensee.
On a related matter, recent news reports have stated that the Nuclear Regulatory Commission is conducting an investigation of allegations made by former workers at the Wolf Creek project about quality-control and documentation problens. An article appearing in the April 5, 1984, edition of the Wall Street Journal quotes agency officials as confirming that an investigation is underway.
I would like to be kept fully and currently informed of the Commission's activities in this case and expect to receive a copy of the findings of this investigative effort as soon as it is complete.
Thank you, in advance, for your attention to these reque :s.
Wit est re r i,
4 D V Glickman MEMBER OF CONGRESS DG:sm cc: Congressman Harold Volkmer Michael Lennen, Chairman, Kansas Corporation Commission Congressman Morris Udall, Chairman Committee on the Interior L.
J