ML19350B014
| ML19350B014 | |
| Person / Time | |
|---|---|
| Site: | Zimmer |
| Issue date: | 02/12/1981 |
| From: | Daniels F, Gwynn T, Warnick R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML19350B010 | List: |
| References | |
| 50-358-81-01, 50-358-81-1, NUDOCS 8103190082 | |
| Download: ML19350B014 (6) | |
See also: IR 05000358/1981001
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U.S. NUCLEAR REGULATORY COMMISSION
OFFICE OF INSPECTION AND ENFORCEMENT
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REGION III
Report No. 50-358/81-01
Docket No. 50-358
License No. CPPR-88
Licensee: Cincinnati Gas and Electric Company
139 East 4th Street
Cincinnati, Ohio 45201
Facility Name:
W. H. Zimmer Nuclear Power Station
Inspection At:
W. H. Zimmer, Moscow, Ohio
Inspection Conducte : Jan ry 5-9, 12-16, 19-23, 26-30, 1981
. Inspectors:
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Approved By:
R.
. Warnick, Chief
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P' jects Section 3
Inspection Summary
Inspection on January 5-9, 12-16, 19-23, 26-30, 1981 (Report No. 50-358/81-011
Areas Inspected:
Routine resident inspection of previously identified items,
IE bulletin followup, plant procedures, operations staff training, preoperational
testing observation, preoperational turnover controls and plant tours. This
inspection involved a total of 158 inspector-hours onsite by the NRC ReFident
Inspectors including 17 inspector-hours onsite during off-shifts.
Results: Of t.he seven areas inspected, six were found satisfactory, and one
noncompliance was identified in the area of preoperational testing observation.
(Violation of 10CFR50, Appendix B, Criterion XI, Test Control, Severity Level V)
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8108190 M
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DETAILS
1.
Personnel Contacted
- J. R. Schott, Station Superintendent
- P. E. King, Assistant Station Superintendent
- J. J. Wald, Station Quality Engineer
J. H. Woeste, IC Engineer
A. L. Mosbaugh, Testing Coordinator
M. R. Jonzen, Testing Engineer
and others of the station staff
- Denotes personnel attending monthly exit meeting.
2.
Licensee Action on Previously Identified Items
Unresolved Item 80-24-01 - Lack of traceability for Engineering Change
Requests (ECR).
The inspector reviewed the latest revision to SU.ACP.13. Processing of
Engineering Change Requests and it now appears that traceability can be
maintained. (Closed)
3.
IE Bulletin Followup
For the IE Bulletins listed below the inspector verified that the written
response was within the time period stated in the bulletin that the
written response included the information required to be reported, that
the written response included adequate corrective action commitments based
on information presentation in the bulletin and the licensee's response,
that-licensee management forwarded copies of the written response to the
appropriate onsite management representatives, that information discussed
in the licensee's written response was accurate, and that corrective action
taken by the licensee was as described in the written resporse.
(Closed)Bulletin 80-24, Prevention of Damage Due to Water Leakage Inside
Containment: The inspector verified there were no open water cooling sys-
.tems inside the containment.
No items of noncompliance or deviations were noted.
4.
Plant Procedures
The inspector reviewed the Wm. H. Zimmer Master Procedures Index of station
administrative and implementing procedures. The requiremerts of Technical Specification 6.8.1 and the recommendations of Regulatory Guide 1.33,
Appendix A were used as the basis for this review. This review is presently.
incomplete and will be the subject of a future inspection report.
No items of noncompliance or deviations were noted.
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5.
Operations staff Training
The inspectors verified that a documented training program censistent with
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the FSAR training commitments for principal plant staff, licensed persernel,
non-licensed personnel and the technicians has been e=tablished and that
responsibilities for administering and evaluation or the training progeams
has been assigned.
a.
Material Reviewed
(1) Documents
Wm. H. Zimmer FSAR, Chapter 13.2, Training Program
ANSI N18.1-1971, Selection and Training of Nuclear Power Plant
Personnel
NUREG 0737, Clarification of TMI Action Plan Requirements
10CFR55, Appendix A. Requalification Programs for Licensed Operato-s
of Production and Utilization Facilities
(2)
Training Records
Two Cold License Senior Reactor Operators
Two Cold License Reactor Operators
Two Startup Test Engineers
Two Instrument and Control Technicians
Two QA/QC Technicians
(3) Procedures
TR. SAD.02, Revision 02, Fire Brigade Training Program
TR. SAD.05, Revision 00, Rad!ological Self-Monitoring Training
Program
TR. SAD.10, Revision' 00, Certified Operator Onsite, Experience, Low
Power Testing and BWR Simulator Refresher Training
.TR. SAD.08, Revision 00, Licensed Operator Requalification Prrgram
4) Training Sessions Attended
Shift Technical Advisor . Lecture' on Integrated Plant Operations
Cold Licensed Operators Lecture on Recognizing and Mitigating the
Consequences of Severe Core Damage
b.
Findings
The requirements setforth in NUREG 0737 and 10CFR55, Apperdix A regard-
ing Requalification Training have not -been incorporated, as of yet, .
into the latest revisions of TR. SAD.08 and TR. SAD.10.
This is considered
to be an' unresolved item and will be'followed up ir subsequert inspec+1ons.
(50-358/81-01-01)
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6.
Preoperational Turnover Controls
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The inspector verified implementation of return to construction (turnback)
activities on the Residual Heat Removal (RH) System per SU.PRP.04, Punch-
list Item completion and Maintenance in Turned Over and Non-Turned Over
Areas. This inspection included a detailed procedure review, interviews
with cognizant personnel, review of turnback logs and files, and veriri-
cation of documentation completeness for selected RH system turnbacks.
a.
Findings
(1) Turnback records and files reviewed appeared to be well kept and
complete.
(2)
Section 3 of form PoJ/-04-2 hat space identified as "QA/QC Documen-
tation Complete" which is no longer required by procedure and
should be deleted. This was discussed with the turnover groue
supervisor who indicated that this deletion would be included in
the next revision of SU.PRP.04.
No items of noncompliance or deviations were noted.
7.
Preoperational Testing Observation
The inspectors observed the performance of Control Rod Drive Hydraulic
Preoperational Test, P0.RD.02, Revision 04.
They attempted to verify
procedural controls were being followed, instruments used te record
acceptanc criteria were properly calibrated, and required orerequisites
were comp .ted.
a.
Material Reviewed
(1)
P0.RD.'02, Revision 04, Control Rod Drive Hydraulic Preoperational
Test
.(2)
IM. SAD.01, Revision 02, Instrument and Control Program
(3). MT. SAD.01, Revision' 05, Control of Measuring and Test Equipment
(4)
SU. ACP.05, Revision' 09, Conduct of Preoperational Tests
(5) CGEE FSAR, Section 14.1.1.2.
b.
Findings
(1)' The following are^ examplas of inadequate testing controls during
'the performance of Preoperational Test P0.RD.02.
-(a)
A' step was added to the procedure between step 7.4.2.5 and
7.4.2.6 without use of a Test-Change Notice.
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(b)
A note after step 7.4.2.6, which required that valve IC11-
D001-F107 he lef t closed, was not followed and when per-
forming step 7.4.2.7 water was blown out of the above valve
onto the floor and personnel performing test.
(c)
A note after step 7.4.2 requires the completion of testing
through Section 7.4.1 with the exception of Sections 7.1.2,
7.2.6 and 7.3.1 as a prerequisite, but upon review of "Of fi-
cial Copy" of the Preoperational Test Section 7.4.1 was not
verified as completed and step 7.4.2 was being performed.
Also, step 7.4.1.54 of Section 7.4.1 was not verified as
being completed.
(d)
A recorder (1C11-R611) used for recording the acceptance
criteria of buffer assembly settle time was 9 months past
due for calibration.
As stated before, the above are examples of inadequate testing
controls and are considered to be in violation of 10 CFR SC
. Appendix B, Criterion XI; CG&E FSAR Section 14.1.1.2, which states
in part that all preoperational and initial startup tests will be
conducted in accordance with approved written test procedures,
administrative controls and supporting administrative procedures;
and the implementing administrative control procedure SU.ACP.05.
(50- 358/81-01-02)
8.
Plant Tours
The inspectors conducted frequent plant tours throughout this inspection
. period. The below items were identified and the licensee is taking or
has taken appropriate corrective action.
a..
Excessive amounts of combustible material was found in the RH Heat
Exchanger Rooms.
b.
Scaffolding using.the cable tray in the HP Room for support,
c.
Flange on discharge of Reactor Water Cleanup Pump leaking.
d.
Nitrogen bottles located by the south CRD hydraulic accumulators not
properly supported.
No items of noncomplianee were identified.
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9.
Unresolved Items
Unresolved items are matters about which more informatien is required in
order to ascertain whether they are acceptable items, items of noncompli-
ance, or deviations. One unresolved item disclosed during this inspection
is discussed in paragraph 5.b.
10.
Management Interview
The inspector met with licensee representatives (denoted in paragraph 1)
at the conclusion of the inspection on January 30, 1981. The inspector
summarized the scope and findings of the inspection.
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