IR 05000275/1987031
| ML17083C006 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon  |
| Issue date: | 09/10/1987 |
| From: | Burdoin J, Mendonca M NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML17083C005 | List: |
| References | |
| 50-275-87-31, 50-323-87-31, NUDOCS 8709290149 | |
| Download: ML17083C006 (10) | |
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U.
S.
NUCLEAR REGULATORY COMMISSION
REGION V
Report Nos.
50-275/87-31, 50-323/87-31 Docket Nos.
50-275, 50-323 License Nos.
Pacific Gas and Electric Company 77 Beale Street, Room 1451 San Francisco, California 94106 Facility Name:
Diablo Canyon Units 1 and
Inspection at: Diablo Canyon Site, San Luis Obispo County, California Inspection Conduc ed u us 24-28, 198 Inspector:
J.
.
Burd in, Reac or Inspector a
e igned Approved by:
M.
M. Mendonca, Chief Reactor Project Section
Date Signed
~Summer:
Ins ection Durin Period of Au ust 24-18 1987 (Re ort Nos.
50-275/87-31 and 50-323/87-31 various vital areas and equipment in the plant, and followup of temporary instruction, Part 21(s),
open items and Nonconformance Reports.
Inspection Procedures Nos.
25019, 25573, 30703, 36100, 71707, 92700 and 92701 were used as guidance for the inspection.
Results:
No violations or deviations were identified.
870+2+0g4P 870 PDR ADOCK 0 PDR
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DETAILS Individuals Contacted Pacific Gas and Electric Com an PG&E)
- J.
D.
Townsend, Acting Plant Manager
~R.
M. Luckett, Regulatory Compliance Engineer R.
G.
Oman, Assistant Project Engineer (Bechtel)
F.
W.
Chan, Electrical Engineer
"L. F.
Womack, Operations Manager T.
L. Grebel, Regulatory Compliance Supervisor M.
W. Stephens, General Foreman, Instrumentation
. T.
A. Nelson, Regulatory Compliance Engineer S.
D. Wilson, Regulatory Compliance Engineer D.
R. Bell, Quality Control (QC) Supervisor, General Construction Various other engineering and QC Personnel.
~Denotes attendees at exit meeting on August 28, 1987.
Area Ins ection An independent inspection was conducted in Units 1 and 2 Turbine and Auxiliary Buildings.
The equipment and areas inspected included:
A.
B.
C ~
D.
E.
F ~
G.
H.I.
J.
K.
L.
M.
N.
Five Emergency Diesel Generator Rooms.
Six 4160 Volt Switchgear Rooms.
Combined Two-unit Control Room.
Four Containment Spray Pumps.
Three Charging Pumps, Units 1/2.
Four Safety Injection Pumps.
Four RHR Pumps.
Six Component Cooling Water Pumps.
Six Auxiliary Feedwater Pumps.
Six 480 Volt Vital Bus Rooms.
Two Cable Spreading Rooms.
Two Hot Shutdown Panel Areas.
Two 480 Volt Load Center Areas.
Turbine Building at Elevations 140'.
Housekeeping and equipment status were acceptable.
No violations or deviations were identified.
Fol lowu of Part
Re orts The licensee's response to the following Part 21 reports were reviewed:
A.
(Closed 86-25-P Non-Environmentall uglified Buchanan 724 Terminal Stri s for Limitor ue 0 erators Arkansas Nuclear Power Plant (ANPP) reported under
CFR 21 that Buchanan 724 terminal strips were supplied as correct replacements for environmentally qualified (EQ) Buchanan 524 terminal strips used-in Limitoque operators.
Upon investigation into the environmental qualification of Buchanan 700 series (including 724) terminal strips, it became apparent the qualification of the terminal strips could not be established.
The inspector examined licensee's documentation which verified that Buchanan terminal strips-are not used in EQ application at the Diablo Canyon Power Plant.
In the case of EQ Limitorque operators, the cables are spliced at the Limitorque operators in lieu of using terminal strips.
This item is closed.
B.
Closed 87-13-P Hain Steam Check Valves Retainin Nut Problem During the first refueling outage of Unit 1 at the Diablo Canyon Power Plant, Surveillance Test Procedure V-18 entitled "Check Valve Inspection" was performed on the main steam line check valves (immediately downstream of the MSIVs).
The inspection revealed that the retaining nut that attaches the check valve disc to its tail link was loose or missing on two of the four check valves.
The licensee to correct the problem redesigned the disc nut locking device and installed the new design on each unit during the units'irst refueling outages.
The following Nonconformance Report (NCR), design change notices (DCNs),
and Quality Control Instructions (QCIs) issued as corrective measures for this problem were examined to verify the completion of the licensee's corrective actions:
NCR, DC1-86-MM-N128-DCN, DC1-SM-37286 DCN, DC2-SM-38286 Main steam check valve MS-1-4062, locking nut missing Revised disc nut locking device Revised disc nut locking device CI Unit 1 CI Unit 2 86-1595-1596-1597-1598-1607-1609-1611
.-1613 87"0294-0295-0296
"0297-0305-0306-0307-0308
The documents were found to be in order and acceptably documented the licensee's actions to correct this problem.
This item is closed.
No violations or deviations were identified.
4.
Followu of NRC Tem orar Instructions TIs TI 2515/73 IE Bulletin 85-03 "Motor-0 crated Valve Common Mode Failures Durin Plant Transients Due to Im ro er Switch Settin s" The inspector as a followup to Inspection Report 50-275/87-11 and 50-323/87-10 selected as a sample, the following ten motor operated valves, from the 19 valves at Unit 2 for which torque/limit switch adjustments had been made during the Unit 2,refueling outage in the Spring of 1987.
The work orders under which the torque/limit switch adjustments were accomplished for the selected valves are listed below:
Valve Nos.
Work Order Nos.
Valve Nos.
.
Work Order Nos.
8106 8107 8807A 8803B 8821B C-0003906 C-0003961 C-0003888 C-0003897 C-0003963 8974A FCV-37 FCV-95 LCV-106 LCV"109 C-0003886 C-0003833 C-0003988
'C-0003914 C-0003966 The inspector examined the work orders for task (work) description, safety/plant impact, initial review/signoff, gC inspection holdpoints/
signoff, summary comments, operability test/signoff, completion verification, etc.
The test data results sheets were examined to verify that the closing thrust for both manual and electrical operation was greater than the required closing thrust but less than the stud yield point thrust.
The records and thrust values were in order and acceptably addressed TI and Bulletin concerns.
The requirements of TI 2515-73/IE Bulletin 85-03 not addressed in this report or Inspection Reports 50-275/86-31, 87-11, 87-20, and 87-23 will be inspected during a subsequent inspection(s)
and reported under Open Item TI 2515/73.
No violations or deviations were identified.
5.
Nonconformance Re orts NCRs The following two NCRs were examined and the licensee's corrective actions were found to be acceptable:
DCO-86-EM-N132 - Incorrect Termination of Eg Conductors DCO-86-EM-N136 - 8703 Motor Lead Extension Wire
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No violations or deviations were identified.
6.
Followu of 0 en Items A.
0 en 50-275/87-01-02 Control of U -to-Date Vendor Manuals The review and examination of licensee's procedures and corrective action to remedy this deficiency were commenced during this inspection.
However, inspection in this area was incomplete and shall be continued during a future inspection.
B.
0 en 50-275/21-72-01 Review Licensee's Res onse to EDS/PAC A
~Findin n
The review of the licensee's actions in this area was commenced during this inspection.
However, inspection is incomplete at this time and shall be continued during a future inspection.
No violations or deviations were identified.
The inspector conducted an exit meeting on August 28, 1987, with the members of the plant staff as indicated in paragraph 1.
During this meeting, the inspector summarized the scope of the inspection activities and reviewed the inspection findings as described in this report.
The licensee acknowledged the concerns identified in the repor '