IR 05000275/1993026
| ML16342A253 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon  |
| Issue date: | 09/08/1993 |
| From: | Ang W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML16342A252 | List: |
| References | |
| 50-275-93-26, 50-323-93-26, NUDOCS 9309290046 | |
| Download: ML16342A253 (12) | |
Text
U. S.
NUCLEAR REGULATORY COMMISSION REGION V
~ll
55-2/5/93-95 d
5 -323/93-25 Docket Numbers:
50-275 and 50-323 License Numbers:
~Fill
~l Pacific Gas and Electric Company Nuclear Power Generation, B14A 77 Beale Street, Room 1451 P.O.
Box 770000 San Francisco, California 94177 Diabl o Canyon Units 1 and
Diablo Canyon Site, San Luis Obispo County, California Ins ection Date:
August 16 through 20, 1993
~lns ectors:
H. Royack, Reactor Inspector z -Fb.
ng, ie
,
Engineering Section f-8- fz
Summary:
Ins ection from Au ust 16 throu h Au ust
1993 Re ort Nos.
50-275 93-26 d:
The area inspected during the announced routine engineering inspection was design modifications.
"Design Changes" was used as guidance for this inspection.
Results:
General Conclusions and S ecific Findin s:
The parts of the design change packages reviewed appeared to be complete and properly documented.
Si nificant Safet Matters:
None 9309290046 930908 PDR ADOCK 05000275
Summar of Violations:
None 0 en Items Summar
No items were opened or closed during this inspectio A
DETAILS Persons Contacted Pacific Gas and Electric Com an Persons attending the August 20, 1993 exit meeting:
M. Burgess, Director, Systems Engineering T. Grebel, Supervisor, Regulatory Compliance J. Griffin, Group Lead, Onsite Project Engineering Group C. Groff, Director, Plant Engineering R. Hess, Assistant Director, Onsite Nuclear Engineering Services J. Hind, Director, Nuclear Safety Engineering K. Hubbard, Engineer, Regulatory Compliance M. Leppke, Assistant Manager, Technical and Support Services D. Miklush, Manager, Operations Services J. Townsend, Vice President and Plant Manager J. Welsch, Supervisor, Operations Training The inspector also interviewed and held discussions with other licensee personnel during the inspection.
Desi n Chan es 37700 The inspector selected three design change packages (DCP's) which the licensee had determined to not require prior NRC approval and one temporary plant modification.
The three DCP's which the inspector reviewed were installed during the Diablo Canyon Unit 2 refueling outage Cycle Five.
The temporary plant modification was a Unit
and 2 jumper installation which remained in effect at the conclusion of the inspection period.
The DCP's and temporary plant modification were:
~
DCP-M-44100, "Unit 2 Residual Heat Removal (RHR) valves HCV-673, HCV-638, and HCV-670 replacement"
~
DCP-N-44752,
"Steam Generator Blowdown System Modifications"
~
DCP-M-48001,
"Service Cooling Mater Heat Exchanger 2-1 and 2-2 Modifications"
~
Temporary Modification/Plant Jumpers, Log Number 91-061,
"Control Room Plant Ventilation Chlorine Monitor CEL-104, 103, 102, and 101" DCP and Tem orar Modification Packa e Ins ection Criteria The inspector reviewed the DCP's and temporary modification for conformance with Technical Specifications,
CFR 50.59 review requirements, licensee's guality Assurance Program and procedures, and
CFR 50, Appendix B, Criterion III, "Design Control."
k
Licensee procedures reviewed for process control were guality Control (gC) procedure gCP-3. 1, "Design Change Activities," Revision 4; Nuclear Engineering and Construction Services (NECS) procedure NECS - E3.6 DC,
"Diablo Canyon Power Plant Changes,"
Revision 0; Nuclear Engineering Services (NES) administrative procedure CF3.NE9,
"Diablo Canyon Power Plant Design Changes,"
Revision 0, and Nuclear Plant Administrative Procedures, NPAP C-1/NPG-4.2,
"Nuclear Power Plant Hodification Program,"
Revision 9, AP C-4Sl,
"Temporary Hodification Control Plant Jumpers,"
Revision 16, and AP C-1Sl,
"Onsite Plant Hodification Administration,"
Revision 13.
Ins ector Actions The inspector reviewed the selected design change packages and temporary plant modification for administrative control, guality Control and Assurance oversight,
CFR 50.59 evaluations, Updated Final Safety Analysis Report (UFSAR) updates, procedure revisions and operator and maintenance personnel training.
The inspector performed a walkdown inspection of the design modifications.
Conclusion The inspector concluded, based on the review of documents for the selected DCP's and the temporary modification, that the licensee had the proper approval authority for the DCP's and temporary modification packages.
The licensee had also implemented appropriate process and procedure control through engineering and design process control, guality Control and guality Assurance oversight, review, and independent verifications.
The inspector concluded, based on a review of licensee
CFR 50.59 review documentation,. that the licensee had performed
CFR 50.59 evaluations and reviews and that the reviews were technically correct.
The inspector also concluded that the licensee had correctly determined that the modifications had not presented any unreviewed safety questions.
The inspector concluded from document reviews that the licensee had prepared UFSAR change notices for the selected design change packages.
The inspector concluded from procedure and test data review that the licensee had post modification test (PHT) procedures for the DCP's, that testing acceptance criteria was defined, and that PHTs had been completed and test results were in accordance with specified acceptance criteria.
The inspector concluded from a review of procedures, lesson plans, and training records, that the licensee had revised operating and surveillance procedures to incorporate the DCP changes.
The licensee had revised operator and maintenance personnel les'son guides to include the design changes and that operating and maintenance and surveillance personnel had received training on the modifications.
The inspector concluded, based on a visual inspection of the design
II
revised operator and maintenance personnel lesson guides to include the design changes and that operating and maintenance and surveillance personnel had received training on the modifications.
The inspector concluded, based on a visual inspection of the design changes, that the licensee had installed the modifications as described in the design change packages.
The inspector concluded, based on a review of licensee records, that the licensee was performing weekly interim status reviews of temporary plant modifications in accordance with licensee procedures.
No violations or deviations of NRC requirements were identified.
k 3. ~Ei<<i The inspector conducted an exit meeting on August 20, 1993, with members of the licensee staff listed in paragraph 1 of this inspection report.
The inspector summarized the scope of the inspection activities and reviewed the inspection findings as described in this report.
At the conclusion of the exit meeting the inspector requested that the licensee identify any proprietary material provided to or reviewed by the inspector during the inspection.
The licensee did not identify as proprietary any of the materials provided to or reviewed by the inspecto bcc w/enclosure:
P. Johnson Project Inspector Resident Inspector G.
Cook B. Faulkenberry Docket File bcc w/o enclosure:
H. Smith J. Zollicoffer J. Bianchi N. Royack y /g/93 P.
sn f /~/3 (pj'a=
W. Ang g /P/93
[
VEST COPY)
Q ST COPY]
[REQUEST QPY]
[
ES /
NO
]
YES
/
NO
]
[YES / ~]
L. Nil qr
/93
[REQUEST COPY]
[YES /
NO
]
[S ND TO PDR ]
ES /
NO
]
0