IR 05000010/1977005
| ML19340A789 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 03/30/1977 |
| From: | Knop R, Shafer W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML19340A787 | List: |
| References | |
| 50-010-77-05, 50-10-77-5, 50-237-77-05, 50-237-77-5, 50-249-77-05, NUDOCS 8009030829 | |
| Download: ML19340A789 (7) | |
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UNITED STATES Ni' CLEAR REGULATORY COMMISSION OFFICE OF INdi>ECTION AND ENFORCEMENT REGICG III
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Report of Operations Inspection IE Inspection Report No. 050-010/77-05 IE Inspection Report 'lo. 050-237/77-05 IE Inspection Report No. 050-249/77-05 Licensee: Commonwealth Edison Company P.O. Box 767 Chicago, IL 60690 Dresdan Nuclear Power Plant License No. DPR-02 Units 1, *. and 3 License No. DPR-19 Morris, LL License No. DPR-25 Category:
C Type of Licensee:
BWR (GE) 200 & 810 MWe Type of Inspection:
Routine, Unannounced
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Dates of Inspection:
March 8-10, and 14-17, 1977 b
bh Principal Inspector:
W. D. Shafer.
3-3o~7 ?
(Date)
Accompanying Inspectors: None other Accompanying Pergonnel: None
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jN Reviewed By:
R. C. Knop, Chief 3 -'3h'7 7
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Reactor Projects Section 1 (Date)
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SUMMARY OF FINDINGS Inspection Summary
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i Inspection on March 8-10 and 14-17, 1977, (Unit 1, 77-05), (Unit 2, 77-05),
and (Unit 3, 77- 05): Review of safety limits, limiting safety system
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settings and limiting conditions for operations (Units 2 and 3).
Review i
of surveillance (Units 2 and 3), licensee event reports (Units 1, 2, and 3)
and HPCI valve internals inspection (Unit 2).
One item of noncompliance l
was identified, relating to record control (Unit 2).
Enforcement Items
Deficiency (Unit 2)
Contrary ~to Technical Specifications Section 6.5.A.1 the APRM No. I and No. 2 recorder chart for December,1976 was not available for review upon request. In general, the licensee's control of log books and recorder charts is inadequate in that any person has free access to these records with no access control provisions. The licensee's immedi-ate response appears adequate, requiring no further response.
(Para-
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g raph 3.c, Report Details)
i Licensee Action on Previously Identified Enforcement Items
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None reviewed.
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l Other Significant Items A.
Systems and Components j
The licensee has inspected and repaired the Unit 2 HPCI discharge valve (No. 1501-8). No significant damage was discernible.
B.
Facility Items (Plans and Procedures)
d The licensee is scheduling a refueling mutage for Unit 1, tentatively planned for May, 1977.
C.
Managerial Items
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j None.
D.
Deviations
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None.
E.
Status of Previously Reported Unresolved Items None reviewed.
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!!r.nagement In t erviet.:
On March 24, 1977, at the conclusion of the inspection, a management interview was conducted with Mr. Stephenson, Station Superintendent
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and other licensee representatives. The inspector stated the following:
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A.
No significant concerns were identified in reviewing Units 2 and 3 compliance to Technical Specification safety limits, limit ng safety system settings and limiting conditions for operatior..
(Paragraph 3, Report Details)
B.
One item of noncompliance, relating to record control, was discussed.
(Paragraph 3.c, Report Details)
C.
The review of Units 2 and 3 surveillance program indicated no significant problers. The inspector commented that the licensee's surveillance program efforts are impressive.
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_ REPORT DETAILS
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1.
Persons Contacted
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B, Stephenson, Station Superintendent i.
A. Roberts, Assistant Superintendent
B. Shelton, Administrative Assistant C. Sargent Technical Staff Supervisor
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C. Lawton, Office Supervisor E. Budzichowski, Operating Engineer, Unit
N. Scott,
Lead Operating Engineer R. Ragan, Operating Engineer, Unit 3 i
D. Adam, Radiation Chemistry Supervisor J. Dolter, Leading Nuclear Engineer J. Kolanowski, Operating Engineer, Unit 2
T. Shaw, Quality Assurance Operations W. Hildy, Instrument Engineer R. Thomas, Instrument Foreman i
R. Ccmpbell, Instrument Foreman R. Falbo, Assistant Office Supervisor j
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C. Reardanz, Technician J. Martin, Engineer R. N1mmer, Surveillance Coordinator G. Romba, Engineer
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H. Waclaw, Engineering Assistant
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2.
_S_urveillance (Units 2 and 3)
The following surveillance test procedures were revie a.
inclusion of prerequisites, acceptance criteria test equipment and operational checks ident
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No concerns we
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DIS 500-2, Lo Reactor Level Scram DIS 500-5, Discharge Volume High Level Scram DIS 500-8, EHC Low Pressure Scram Point
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DIS 1300-2, Isolation Condenser Steam Line High
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DIS 1400-3, Core Spray Low Pressure on Auto ECC
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DIS 1600-4, Drywell High Pressure
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DIS 1600-10, 0 Analyzer System
SOP 178, Recirculating Pump Speed Mismatch
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b.
The inspector witnessed a surveillance test on the re pump mismatch on Unit 2.
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MV/I Units, proportional amplifier and mismatc
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l for both A and B pumps. No significant r
i-concerns were ic !
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REPORT DETAILS
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Persons Contacted
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B. Stephenson, Station Superintendent i
A. Roberts, Assistant Superintendent B. Shelton, Administrative Assistant C. Sargent, Technical Staff Supervisor i
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C. Lawton, Of fice Supervisor
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E. Budzichowski, Operating Engineer, Unit 1 N. Scott, Lead Operating Engineer -
R. Ragan, Operating Engineer, Unit 3 q
D. Adam, Radiation Chemistry Supervisor j
J. Dolter, Leading Nuclear Engineer
J. Kolanowski, Operating Engineer, Unit 2 T. Shaw, Quality Assurance Operations W. Hildy, Instrument Engineer R. Thomas, Instrument Foreman
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R. Ccmpbell, Instrument Foreman R. Falbo, Assistant Office Supervisor C. Reardanz, Technician J. Martin, Engineer R. Nimmer, Surveillance Coordinator G. Romba, Engineer
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H. Waclaw, Engineering Assistant 2.
Surveillance (Units 2 and 3)
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The following surveillance test procedures were reviewed for
a.
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inclusion of prerequisites, acceptance criteria, identification of test equipment and operational checks. No concerns were identified.
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DIS 500-2, Lo Reactor Level Scram DIS 500-5, Discharge Volume High Level Scram
DIS 500-8, EHC Low Pressure Scram Point DIS 1300-2, Isolation Condenser Steam Line High Flow DIS 1400-3, Core Spray Low Pressure on Auto ECCS Blowdown DIS 1600-4, Drywell High Pressure
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DIS 1600-10, 0 Analyzer System i
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S0P 178, Recirculating Pump Speed Mismatch
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b.
The inspectcr witnessed a surveillance test on the recirculating pump mismatch on Unit 2.
The test included calibration of the
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i MV/I Units, proportional amplifier and mismatch alarm units for both A and B pumps. No significant concerns were identified.
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c.
For those surveillance tests identified in 2.a about the
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inspector determined that test frequency, supervisory review, I-
'and reporting requirements were accomplished in accordance j
with Technical Specification requirements.
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Review of Safety Limits (SL), Limiting Safety System Settings (LSSS),
and Limiting Conditions (LCO) for Operations (Units 2 and 3)
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a.
The following SL, L9SS, and LCO's were reviewed to determine t
the licensee's conformance with the Technical Specifications.
The review included direct observations, review of recorder i
charts, survei]L?nce requirement records, and equipment tagout
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logs.
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j (1) ~ Reactor Pressure JL 1325 psig, SL l
Reactor Pressure scram 11060 psig LSSS, LCO
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(2) Flux Scram Setting Limit 411.5 Seconds, SL APRM Flux Scram setting, LSSS, LCO r
(3) Recirculating Pump Mismatch, LCO i-
(4) - Primary Coolant Leakage, LCO
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t (5) Torus Pool Temperature, LCO
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(6) HPCI Operability, LCO (7) Condensate Pump Room Flood Protection, LCO
(8) Diesel Fuel Requirements, LCO
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-b.
In reviewling the Unit 2 recirculating pump flow recorder charts the inspector noted that on several occassions an LCO appeared to have been exceeded. Further review involving
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observation of the recirculating pump mismatch surveillance (Paragraph 2.b, Report Details). indicated that the observed error be: ween the recorded pump flow rates and indicated
pump speed appears to be in the flow recorder. There is
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no record of calibration frequency on the flow recorder. A licensee representative stated that all calibration or
work accomplished on the flow recorder is accomplished by
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work request.
In a previous inspection 1/ the inspector identified a non-
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compliance relating to lack of calibration of those components
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associated with safety'related systems. The previously j
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l 1/ IE-inspection Report No. 050-237/76-28.
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i discussed flow recorder is identifiable as the type of equipment the licensee was cigpd for not calibrating. The
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licensee's corrective-actionst is a commitment to prepare
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and implement a calibration schedule for this equipment by
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September 30, 1977. With respect to the recirculating pump flow recorder, no further action will be taken at this time.
c.
In reviewing the APRM recorder charts the inspector deter-mined the chart for APRM No. 1 and No. 2 for December, 1976 to be missing. An immediate search for the missing chart failed to locate it.
The licensec was informed that the lack of maintaining this record is contrary to Technical Specifications 6.5.A.l and is an item of noncompliance.
A licensee representative stated that the maintenance of historic log books and recorder charts will be bnmediately
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controlled by requiring personnel to " sign out" for them and by keeping the logs and recorder charts under lock and key.
The inspector informed the licensee the noncompliance will require no further response.
4.
Licensee Event Report Review (Units 1, 2, and 3)
e a.
The following licensee event reports were reviewed for proper
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' reporting requirements, corrective action, licensee review
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and safety of operations.
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Unit 1 RO 50-10/77-2, Failure to sample water during startup.
Unit 2 RO 50-237/76-64, Unit 2 diesel generator failed to start.
RO 50-237/76-70, Unit 2 diesel generator failed to carry required load.
i RO 50-237/76-71, Exceeded surveillance intervals.
RO 50-237/77-2, Nonconservative APRM flow biased scram setpoints.
RO 50-237/77-5, LPCI cross-tie valve 1501-32B failure.
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Unit 3 RO 50-249/76-28, Unit 3 250 Volt battery declared inoperative.
b.
With respect to RO 77-2 (Unit 1), 76-71 (Units 1, 2, and 3), and
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77-2 (Unit 2) the inspector determined that the items had been identified, reported and corrected by the licensee. No further concerns were were identified by the inspector.
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c.
The following licensee event reports were reviewed in-office.
No concerns were identified.
2/ Ltr, Bolger to Keppler, dtd 2/28/77.
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I Unit-1 i
- RO 50-10/76-19, Exceeded surveillance intervals.
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Unit 2
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RO 50-237/76-72, CRD J-11 uncoupled (Reviewed onsite,
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IR 237/76-28)
RO 50-237/76-73, Units 2 and 3, N storage tank low level.
Unit 3 RO 50-249/76-32, Unit 3 diesel generator engineer speed failure.
i RO 50-249/76-36, Exceeded surveillance intervals.
l RO 50-249/77-1, DP indicating switch failed open.
5.
General l
On March 17 1977, during a Unit 2 maintenance outage the i
inspector observed a visual inspection of the hPCI discharge valve internals (Valve 1501-8), conducted by the licensee.
There were no apparent visual indications of severe damage i
to the valve body as a result o the bent stem problem 13,1976.jf
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occurring on November Upon completion of repairs to valve 1501-8, the licensee will leave the valve locked open pending final resolution of a wiring problem, identified on the
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identical valve in the Unit 3 HPCI system.
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3/ Ltr, Stephenson to-Keppler, dtd 11/26/76 (LER 50-237/76-66).
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4,/ LER 50-249/76-34.
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