ML20031H283
| ML20031H283 | |
| Person / Time | |
|---|---|
| Site: | Zimmer |
| Issue date: | 10/21/1981 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20031H277 | List: |
| References | |
| 50-358-81-22ERR, NUDOCS 8110270323 | |
| Download: ML20031H283 (2) | |
See also: IR 05000358/1981022
Text
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(4) The following labeling discrepancies were noted on the E1010
schematic drawings:
(a) E1010/Pg.NB23, auxiliary relay K-80 is labeled "Close
RHR Head Spray, Suction and Shutdown' Cooling Injection
Valves." This relay actually operates only the inboard
RHR shutdown cooling suction isolation valve.
(50-358/81-22-07)
(b) -E1010/Pg.NB29, auxiliary relay K29 and K30 logic includes
contacts from 1E31-N012A and B which are labeled "0 PENS
ON HI VIR LEV."
These contacts actually represent a hi
flow rate containment isolation signal for the RHR shut-
down cooling suction line.
(50-358/81-22-08)
No items of noncompliance or deviations were noted.
6.
Review of Valve Packing Leak Detection Requirements Inside Containment
The inspector reviewed the plant design with respect to provision for
identification of valve packing leakage inside the primary containment.
This included a review of reguiatory requirements, FSAR commitments,
design specifications, design drawings, and the as built condition of
the plant. This review was initiated in response to Section 5.b(2)(b)
of this inspection report.
a.
Documentation Reviewed
(1)
10 CFR 50, Appendix A, Criterion 30
(2)
Wm. H. Zimmer FSAR
(3) GE Design Specification 22A2817, Revision 03, Residual Heat
Removal System
(4) GE Design Specification Data Sheet 22A2817AJ, Revision 05,
Residual Heat Removal System
(5) S&L Piping and Instrument Detail Drawings (various)
(a) P&ID M-21, Main Steam System
(b) P&ID M-49, High Pressure Core Spray
(c) P&ID M-50, Low Pressure Core Spray
(d) P&ID M-51, Residual Heat Removal System
(e) P&ID M-52, Reactor Core, Isolation Cooling System
(f) P&ID M-83, Nuclear Boiler System
(g) P&ID M-84, Leak Detection System
b.
Findings
(1)
10 CFR 50, Appendix A, Criterion 30 requires, " Components
which are part of the reactor coolant pressure boundary shall
be designed, fabricated, erected, and tested to the higaest
quality standards practical. Means shall be provided for
detecting and, M the extent practical, identifying the
8110270323 811021 4;
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location of the source of reactor coolant leakage." 'The
W . H. Zimmer FSAR, Paragraph 5.2.7.1.2.j. states, " Valve
m
Packing Leakage - Valve stem packing leaks of. power-operated
valves-in the nuclear boiler system, high pressure core spray,
low pressure core spray, reactor core isolation cooling system,
residual heat removal system, and recirculation system are
detected by monitoring packing leakoff for high temperature
sud are annunciated by an alarm in the control room."
The inspector reviewed the aforementioned system P&ID drawings
and identified the following discrepancies:
(a) RHR System Head Spray Inboard Containment Isolation
Check Valve IE51F066 is provided with leak-detection
capability but no provision has been made to utilize
it.
(b) Main Steam Line Drain Inboard Containment Isolation
Valve 1B21F016 (nuclear boiler system) is identified
on Drawing M-21, Sheet 4 as being provided with leak-
detection capability (line ILD49A 3/4 referenced.to
M-84 Sheet 3).
Review of M-84 Sheet 3 revealed that
no provision had been made for leak detection on this
valve. A field check of the as-built condition ver-
ified that line ILD49A 3/4 was not installed.
(c) Main steamline vent (head vent and vent to radwaste)
Valves IB21F001, F002, F005 and RCIC steamline drain
Valva 1E51F076 are reactor. coolant pressure boundary
valves, power-operated, and located inside the primary
containment which are not provided with leak detection
capability.
These items are unresolved pending review by.the licensee
and by the NRC Office of Nuclear Reactor Regulation,
Division of Licensing.
(50-358/81-22-09)
No items of noncompliance or deviations were noted.
7.
Plant Tours
The inspectors conducted frequent plant tours throughout this inspec-
tion period. The below listed items were identified ind the licensee
is taking or has taken appropriate correctivo action:
a.
A diesel generator building roof drain was plugged, causing water
to fall on safety-related cable trays in the
'B'
diesel generator
room. This drain was immediately cleared by licensee personnel.
b.
The following items were noted during a tour of the service water
pump structure:
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(1) Scaffold being supported by ESS Division I and II boxes
JBPB56 and JBPB57.
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