ML20205T098
| ML20205T098 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 04/01/1987 |
| From: | Gagliardo J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | Trevors G NEBRASKA PUBLIC POWER DISTRICT |
| Shared Package | |
| ML20205T102 | List: |
| References | |
| TAC-42486, TAC-68378, NUDOCS 8704070212 | |
| Download: ML20205T098 (5) | |
See also: IR 05000298/1986028
Text
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In Reply Refer To:
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Docket: 50-298/86-28
Nebraska Public Power District
ATTN: George A. Treurs
Division Manager - Nuclear Support
P. O. Box 499
Columbus, NE
68601
SUBJECT:
EQUIPMENT QUALIFICATION (EQ) INSPECTION - COOPER NUCLEAR STATION
INSPECTION REPORT 50-298/86-28
This refers to the first round special team inspection to review compliance
with 10 CFR 50.49, of activities authorized by License No. DPR-46, conducted by
Mr. A. R. Johnson and other NRC representatives on November 3-7, 1986, at the
Cooper Nuclear Station. The team's findings were discussed with you and
members of your staff at the conclusion of the inspection.
Areas examined during the inspection included your implementation of a program
for establishing and maintaining the qualification of electric equipment within
the scope of 10 CFR 50.49. The inspection also included evaluations of the
implementation of EQ corrective action commitments made as a result of
identified deficiencies of (1) the January 30, 1985 Safety Evaluation
Report (SER); (2) the December 9, 1982 SER and November 24, 1982 Franklin
Research Center Technical Evaluation Report (TER) enclosed with it; and
(3) ycur proposed n,ethod of resolution for each of these EQ deficiencies
documented in Nebraska Public Power District's (NPPD) response letter to NRC of
April 24, 1984, regarding the March 29, 1984 meeting between NPPD and NRC.
Within these areas, the inspection consisted of the examination of selected
procedures and records, interviews with personnel, and observations by the NRC
inspectors. The inspection findings are documented in the enclosed inspection
report.
The inspection determined that you have implemented a program to meet the
requirements of 10 CFR 50.49. Nine deficiencies with respect to your program
implementation, involving EQ documentation files and physically installed
configurations of equipment in your plant, are sumarized in Appendix A and are
classified as Potential Enforcement / Unresolved items requiring further action.
The nine Potential Enforcement / Unresolved Items represent failures to fully
establish the qualification of the following equipment:
Boston Insulated Wire
(Bostrad 7E and Coaxial RG59B/4) cable, Kerite HTK/FR 600V cable, Raychem
(Rayolin R and F) coaxial cable, General Electric electrical penetrations.
Limitorque motor operators (SMB Series) Okonite motor lead splices, and Fenwal
temperature switches. Nineteen concerns are classified as Open items and a
future NRC inspection will review or ctions concerning.them.
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Your corrective actions regarding the identified deficiencies in the enclosed
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inspection report should not be delayed pending a future NRC Region IV
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inspection.
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We are available to discuss any questions you have concerning this inspection.
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Sincerely,
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"Drt:rinal SI8"
J. E. GAGUARDO
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J. E. Gagliardo, Chief
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Reactor Projects Branch
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Enclosures:
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Appendix A - Potential Enforcement Unresolved Items
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2.
Appendix B - NRC Inspection Report
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50-298/86-28
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cc w/ enclosures:
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Guy Horn Division Manager
of Nuclear Operations
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Cooper Nuclear Station
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P. O. Box 98
Brownville, Nebraska
68321
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Kansas Radiation Control Program Director
Nebraska Radiation Control Program Director
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APPENDIX A
U.S. NUCLEAR REGULATORY COMMISSION
REGION IV
Potential Enforcement / Unresolved Items
As a result of the special equipment qualification (EQ) inspection of
November 3-7, 1986, the following items have been identified by Region IV as
Potential Enforcement / Unresolved Items (paragraph references are to the
detailed portions of the inspection report).
1.
Contrarytoparagraphs(f)and(k)of10CFR50.49andSection5.2.5of
the D0R Guidelines, the EQ documentation files (EQF) for (1) Boston
Insulated Wire (BIW) cable, type Bostrad 7E, EQ Data Package (EQDP) No. 6,
did not adequately demonstrate qualification because of failure to show
that the equipment functional performance requirements were satisfied.
The analysis used a 20 foot length of cable from the supporting type test,
rather than the fully installed cable length (including considerations
given to splices and penetrations in the cable runs), of the installed
configuration at the CNS plant (paragraph 4.f(1), 50-298/8628-01).
2.
Contrary to paragraphs (f) and (j) of 10 CFR 50.49, the EQF for BIW
coaxial cable, type RG 59 B/4, EQDP No. 6A, did not document and
demonstrate qualification in that BIW test report No. 76J049 was not
auditable to permit verification that this item is qualified for its
application. The documented test report was incomplete, consisted of
only a single page summary, and was not traceable to permit independent
verification of conclusions (paragraph 4.f(2), 50-298/8628-02).
3.
Contrary to paragraphs (f) and (k) of 10 CFR 50.49 and Section 5.2.5 of
the D0R Guidelines, the EQF for Kerite 600 volt cable, type HTK/FR, EQDP
No.5,didnotadequatelysupportqualificationinthat(1)thedocumented
test results did not meet the acceptance criteria of adequate insulation
resistance during DBE testing; and (2) numerous failures during the post
DDEhighpottestoccurred(paragraph 4.f(3),50-298/8628-03).
4.
Contrary to paragraphs (f) and (k) of 10 CFR 50.49 and Section 5.2.2 of
the 00R Guidelines, the EQF for Raychem Coaxial Cable, type Rayolin R and
Rayolin F, XLPE, EQDP No. 4, did not adequately demonstrate qualification
because of failure to demonstrate similarity between the tested and
installed cables. The claim for material similarity in the analysis is
unclear (paragraph 4.f.(5),50-298/8628-04).
5.
Contrary to paragraphs (f) and (k) of 10 CFR 50.49 and Section 5.2.2 of
the 00R Guidelines, the EQF for General Electric (GE) electrical power and
control penetrations, type 238X600NSG1, EQDP No. 8, did not adequately
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establish qualification because of failure to demonstrate similarity
between the tested and installed ccirponents. The analysis in the EQDP was
inadequate in that no link between the test results and the installed
electrical penetrations F01-NS02, F01-NS03, and F01-NSO4 at CNS, was
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available(paragraph 4.f.(6),50-298/8628-05).
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6.
Contrary to paragraphs (f) and (k) of 10 CFR 50.49 and Section 5.2.6. of
the D0R Guidelines, the EQF for various pressure / level switches and
transmitters contained in EQDP No's. 12, 13, 36, 37, 49, 76, 81, 217, 222,
and 228, did not adequately establish qualification because the equipment
documentation failed to address mounting, orientation, and interface
requirements.
From the EQF, it could not be verified that the equipment
in the CNS as-built configuration was installed as tested
(paragraph 4.f.(7), 50-298/8628-06).
7.
Contrary to (f) and (k) of 10 CFR 50.49, and Section 5.1 of the D0R
Guidelines, the EQF for Fenwal/Patel temperature switches, Model
No. 01-170230-090, EQDP No. 220A, did not adequately establish
qualification because of failure to base the qualification of the
interfacing cable splices on full accident conditions including service
life for radiation and aging effects.
The T&B STA-KON fricti7n cr"ged
splices were qualified for steam testing only (paragraph 4.f(8),
50-289/8628-07).
8.
Contrary to paragraphs (f) and (k) of 10 CFR 50.49, and Sections 4.3, 5.1,
and 5.2 of the D0R Guidelines, the EQF for 25 Limitorque motor operators,
model SMB series, did not adequately establish qualification as follows:
a.
No supporting analysis was available in the EQF to address the HELB
accident conditions in which glass braided butyl rubber
(polybutadiene) insulated, internal jumper wire, was used.
b.
No documentation was available in the EQF, to substantiate (by test
results or other laboratory methods) the similarity of material
construction of the internal wiring reported to the NRC by the
licensee in their equipment operational analysis (E0A) Attachment B
which correlated like wiring removed from similar equipment at CNS.
c.
No qualification analysis and test reports were available in the EQF
to support qualification of Scotch taped cable splices, and
unidentified blind barrel cable splices, in eight Limitorque motor
operators.
In the above items
a.,
b.,
and c., the licensee failed to demonstrate
similarity between the tested motor operator configuration and the
installed configurations with regard to materials of construction
(paragraph 4.g, 50-298/8628-08).
9.
Contrary to paragraphs (f) and (k) of 10 CFR 50.49 and Section 5.2.2 of
the D0R Guidelines, the EQF for Limitorque motor operator, Series SMB,
particularly Okonite motor lead splices, found in EQDP No. 31A (B0003
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qualification series), did not adequately establish qualification because
of failure to demonstrate similarity between the splice type tested and
those installed in motor operators at the CNS plant.
No evidence was
contained in the EQF which could demonstrate qualification of Okonite
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splice installations over braided jacket motor leads.
The EQDP in the EQF
only demonstrates Okonite motor lead splice testing over unjacketed
insulated cable (paragraph 4.h(1)(a), 50-298/8628-09).
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