ML20204E233
| ML20204E233 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon  |
| Issue date: | 03/20/1987 |
| From: | Merschoff E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| To: | Shiffer J PACIFIC GAS & ELECTRIC CO. |
| Shared Package | |
| ML20204E236 | List: |
| References | |
| NUDOCS 8703250654 | |
| Download: ML20204E233 (5) | |
See also: IR 05000275/1986033
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION
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WASHINGTON, D. C. 20666
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March 20, 1987
Docket Nos. 50-275 and 50-323
Pacific Gas and Electric Company
ATTN:
Mr. James D. Shiffer, Vice President
Nuclear Generation Department
77 Reale Street, Room 1435
San Francisco, California 94106
Dear Mr. Shif#er:
SUBJECT:
INSPECTION PEPORT N05. 50-275/86-33, 50-323/86-31
Enclosed is the report of the team inspection cenducted by Mr. S. D. Alexander
and other NRC representatives during the period of December 15 through 19, 1936
at the Diablo Canyon Power Plant, of activities authorized by hRC License Nos.
The team's findings were discussed with you and members of
your staff at the conclusion of the inspection.
The inspectors reviewed your
implementation of a program as required by 10 CFR 50.49 for establishing and
maintaining the environmental cualification (EQ) of electrical equipment within
the scope of 10 CFR 50.49. Within these areas, the inspection consisted of
examination of selected procedures and records, inspection of selected plant
equipment, interviews with personnel, and other observations by the inspectors.
The inspectors determined that you have implemented a proaram to meet the
requirements of 10 CFR 50.49 except for certain deficiencies identified in the
enclosed inspection report.
Four of these deficiencies, summarized in
Appendix A, are classified as Potential Enforcement / Unresolved Items and will
he referred to the NRC Rec 2 ion V office for further action.
These defiriencies
related to incomplete spebification of functional performance requirements #or
Conax containment sump temperature sensors and reactor coolant loop subcooling
margin temperature sensors, failure to upgrade (or .iuttify not opgredirg) to
10 CFR 50.49 requirements the level of qualification of a tape and putty solice
insulation system used on equipment qualified to 10 CFR 50.49, lack of submer-
ger.ce type test on Minco temperature sensors subject to submergence used fnr
reactor vessel level indication system density compensation and leck of gear
case ' grease relief valves on certain in-containment Limitorque motorized valve
actuators.
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B703250654 870320
ADOCK 05000275
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Pacific Gas and Electric Company
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March 20, 1987
Four additional concerns were classified as Open Items, and a future NRC
inspection will review your actions concerning them.
Details of all the
deficiencies and concerns are discussed in the enclosed inspection report.
Corpletion of your corrective actions regarding the identified deficiencies
and concerns should not be delayed pending either a future NRC inspection or
further action by the NRC Region V Office.
We are available to discuss any questions you may have concerning this
inspection.
Sincerely,
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E lis W. M'erschoff,
ting Chief
Vendor Program Bra
Division of Quality Assurance, Vendor
and Technical Training Center Programs
Office of Inspection and Enforcement
Enclosures:
1.
Appendix A - Potential Enforcement / Unresolved Items
2.
Appendix B-Inspection Peport Nos. 50-275/86-33 and 50-323/86-31
cc w/ enclosures
Pacific Gas & Electric
ATTN:
C. Coffer, Supervisor
Nuclear Regulatory Affairs
77 Beale Street
San Francisco, California 94106
Pacific Gas & Electric
ATTN:
R. Oman, EQ Task Force Coordinator
77 Beale Street
San Francisco, California 94106
Pacific Gas & ETectric
ATTN:
J. Blakely, Special Projects
Nuclear Regulatory Affairs
77 Beale Street
San Francisco, California 94106
Diablo Canyon Power Plant
ATTN:
R. Thornberry
Plant Manager
P. O. Box 56
Avila Beach, CA 93424
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March 20, 1987
, Distribution:
'llWtc rmak
Locil'PDR
.IEDocketFiles(50-275/323)
DQAVT Reading
VPB Reading
JTaylor.
BGrimes
.HMiller
UPotapovs
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-GHubbard
RWilson
RLasky
HWalker, PAEI/NRR
HSchierling,' PAD 3/NRR
MYost, INEL
RCarpenter, INEL
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RVanderbeek, INEL
DBeahm, INEL
MJacobus, SNL
REGION V DISTRIBUTION:
JMartin, ADM, RV
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DKirsch, (A)D:DRS&P
RPate,(A)C:RSB,DRS&P
SRichards, C:ES, RSB
DWillett, ES,RSB
AChaffee, C:RPB,
MMendonca, C:RPS1, RPB
JBurdoin, RPS1, RSB
Diablo Canyon Power Plant
ATTN:
P. Narbut, USNRC Senior Resident Inspector,
Post Office Box 396,
Avila Beach, CA 93424
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Distribution:
NRC PDR
Local PDR
IE Docket Files (50-275/323)
DQAVT Reading
VPB Reading
JTaylor
'
BGrimes
HMiller
UPotapovs
SAlexander
GHubbard
RWilson
RLasky
HWalker, PAEI/NRR
HSchierling, PAD 3/NRR
MYost, INEL
RCarpenter, INEL
RVanderbeek, INEL
DBeabm, INEL
MJacobus, SNL
REGION V DISTRIBUTION:
JMartin, ADM, RV
DKirsch,(A)D:DRS&P
RPate,(A)C:RSB,DRS&P
SRichards, C:ES, RSB
DWillett, ES,RSB
,
AChaffee, C:RPB,
MPendonca, C:RPS1, RPB
JBurdoin, RPS1, RSB
Diablo Canyon Power Plant
ATTN:
P. Narbut, USNRC Senior Resident Inspector.
Post Office Box 396,
Avila Beach, CA 93424
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APPENDIX A
Potential Enforcement / Unresolved Items
As a result of the equipment qualification inspection during the period of
December 15 through 19, 1986 at the Pacific Gas and Electric Company's (PGAE)
Diablo Canyon Power Plant (DCPP), the following items have been referred to the
NRC Region V office as Potential Enforcement / Unresolved Items.
(Paragraph
references in parentheses are to detailed portions of the inspection report.)
1.
Contrary to paragraphs (f) and (k) of 10 CFR 50.49 and sections 2.2 and
5(1) of NUREG 0588, Category II, PG&E did not establish complete
functional performance requirements for safety-related Conax RTDs in that
the required accuracy for the RTDs was specified in the file as " 1.75 F",
but there were no criteria or standard values established with which to
evalute the data against this specification. Examination of the raw data
showed that several of the semples during the design basis event simula-
tion deviated from the others by nore than 1.75 F.
(Paragraph 4.0(1),
Items 50-275/86-33-01 and 50-323/86-31-01)
2.
Contrary to paragraphs (f) and (k) of 10 CFR 50.49 and Sections 2.2, 2.4
and 5(1) of NUREG-0588, Category II, PG8E had not established cualifica-
tion for safety-related Minco resistarce temperature detectors (RTD)
subject to submergence in that documentetion of a submeroence type test
was not provided. (Paragraph 4.0(2), Items 50-275/86-33,50-323/86-31-02)
3.
Contrary to paragraphs (f) and (k) of 10 CFR 50.49 and section 5(1) of
NUREG 0588, Category II, the qualification documentation for Limitorque
motorized valve actuators (ID No.: 8703) did not establish sirilarity
between the installed actuator and that tested in that, unlike that tested,
there was no gear case grease relief on the installed actuator. The files
contained no analyses to demonstrate that grease reliefs were not required
for the DCPP applications.
(Paragraphs 4.D(6) and 4.E(4), Items 50-275/
86-33-03 and 50-323/86-31-03)
4.
Contrary to paragraph (1) of 10 CFR 50.49, PG&E had not upgraded to
10CFR 50.49 requirements the level of cualification of their Scotch 33*/
Scotchco putty cable splice insulation system used on qualified equipment
purchased after the effective date of 10 CFR 50.49 (February 22,1983)
and the file contained no sound reasons to the contrary. (Paragraphs
4.E(6), Items 50-275/86-33-04 and 50-323/86-31-04)
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