IR 05000010/1975007
| ML20037B014 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 05/16/1975 |
| From: | Dance H, Shafer W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20037B013 | List: |
| References | |
| 50-010-75-07, 50-10-75-7, 50-237-75-12, 50-249-75-10, NUDOCS 8009020596 | |
| Download: ML20037B014 (6) | |
Text
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j U. S. NUCLEAR RECULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
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REGION III
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Report of Operations Inspection i
l IE Inspection Report No. 050-010/75-07
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IE Inspection Report No. 050-237/75-12
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IE' Inspection Report No. 050-249/75-10
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Licensce:
Commonwealth Edison Company P.O. Box 767 Chicago, Illinois 60690 Dresden Nuclear Power Station License No. DPR-2 Units 1, 2, and 3 License No. DPR-19 Morris, Illinois License No. DPR-25 Category:
C Type of Licensee:
GE BWR, 200 and 810 MWe Type of Inspection:
Routine, Unannounced
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Dates of Inspection:
April 21-24, 1975 Dates of Previous Inspection:
March 19-21, 27, April 1-4 and 8-10, 1975 (REP)
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Principal Inspector:
W. D. Shafer GF - f ()->fr U).h.No (Date)
Accompanying Inspector:
None i
Other Accompanying Personnel:
None
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s / / /)D5I Reviewed By:
11. C. Dance, or Reactor nspec or s)i Nuclear Support j/ (Da Le)
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SUMMARY OF FINDINGS _
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Enforcement Action Violations None.
Infractions
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p-None.
- Deficiencies
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None.
Licensee Action on Previously Identified Enforcement Matters The corrective actions for Infraction No. 3 and Deficiency No. I listed in the licensee's response to our letter of March 27, 1975, were reviewed.
Corrective actions related to th'c items have been completed.
(Paragraph 7, Report Details)
Unusual Occurrences
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Nor.e.
Other Significant Findings
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A.
Current Findings Deviation Contrary to Licensee's FSAR commitment, the turbine room secondary containment airlock interlock failed to function properly.
The licensee repaired the interlock prior to the conclusion of this inspection.
B.
Status of Previously Reported Unresolved Items None.
Management Interview The inspector conducted a management interview with Mr. Stephenson, Station Superintendent, and other licensee representatives.
The following matters were discussed:
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A.
The inspector stated that in reviewing plant operations he identified
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the following:
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1.
While passing through the turbine airlock access the inspector noted that the interlock, which allows opening only one door at
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a time, was not in operation.
The inspector staced that this was a devittion from the licensee's FSAR commitment.
The licensee representative stated that the airlock has been repaired and is functioning properly.
2.
The inspector commented that housekeeping around the outer torus catwalk was in need of attention.
(Paragraph 4, Report Details)
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Management agreed that this problem can be corrected by providing trash receptacles in protective clothing change areas.
3.
The inspector stated that in reviewing Units 1, 2 and 3 jumper log books, he noted that procedure DAP 2-8, dated 1975, was not being used.
(Paragraph 6, Report Details)
B.
The inspector stated that in reviewing the surveillance requirement for the Dresden 3 refueling outage, he noted that SRM Channel 24 had not been functionally tested, but the master data sheet was signed off
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indicating completion.
(Paragraph 2.b, Report Details)
The licensee stated that a second SRM functional test had been completed and that was the reason the master data sheet was signed off.
However, he also stated that the second functional test had j
been misplaced, and a search is in progress.
Subsequent to this inspection the inspector received a copy of the missing functional test and after revieuing the data, considers j
the matter closed.
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REPORT DETAILS
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Persons Contacted
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B. Stephenson, Station Superintendent A. Roberts, Assistant Superintendent D. Butterfield, Administrative Assistant R. Ragan, Unit 3 Operating Engineer D. Adam, Radiation Chemistry Supervisor.
p T. Lang, Staff Engineer i
R. Cozzi, Surveillance Engineer
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J. Dolter, Station Nuclear Engineer T. Josefik, Nuclear Station Operator
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R. Lisy, Nuclear Station Operator J. Sierzant, Nucicar Engineer D. Simpson, Refueling Foreman H. Whitehead, Shift Engineer T. Rausch, Nuclear Engineer E. Montanus, Nuclear Station Operator t
F. Stellwag, Refueling Foreman E. Petrowski, Nuclear Engineer W. Joyce, Training Supervisor 2.
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Refueling Preparation (Unit 3)
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a.
Refueling Procedures The inspector noted that the licensee's refueling procedures in
Section 800 of the equipment manual, (Systems Procedures, Chapter
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32) in particular, procedures 800-1 through 800-22, except 800-19,
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have been revised and comply with ANS1 18.7-1972.
Proper administrative review and approval was conducted as required by i
Technical Specifications, Section 6.
The inspector reviewed without comment, the following procedures i
for content:
DFP800-1
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Master Refueling Procedure, April, 1975.
DFP800-3
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Nuclear Fuel Receiving Inspection and Core Preparation of Fuel Bundle, March, 1975.
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j DFP800-7 Fue) Handling Inside the Reactor, March, 1975'.
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DFP800-9 Fuel Movements Between Reactor and Spent Fuel
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Storage Pool.
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Fuel Movements Between Spent Fuel Storage Pool
and Reactor.
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37-9-7, Out of Core Sipping Procedures for Dresden 2/3, February, m
1975.
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The inspector noted that no procedure exists for inspecting fuel which was previously used in the reactor.
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b.
Surveillance Testing The inspector reviewed the surveillance requirements for refueling i
activities and noted that SRM Channel 24 was not functionally tested prior to core alterations, licwever, a master check data sheet No. 800-51 requiring completion of procedure data sheet DFP800-S-III was signed off as having been completed. A licensee representative produced a weekly IM su.rveillance test which established that all four SRM Channels had been functionally tested on April 15, 1975.
The inspector noted the validity of the IM surveillance test and ascertained that the weekly time limit had not elapsed.
Further review revealed that two SRM functional test data sheets exist through administrative procedural overlap.
Additional surveillance requirements were reviewed without comment, as follows:
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(1) Refueling interlock check.
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(2) SRM response.
(3) Fuel pool level.
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(4)
Shorting links removal.
(5) Control blade guide inspection.
3.
Refueling Activities The inspector verified by record review and direct observation that the follouing activities were being conducted in accordance with approved procedures and Technical Specifications.
The only discrepancy noted was the failure of the turbine room airlock interlock.
The inspector identified this interlock malfunction as a deviation from the licensee's FSAR commitment.
a.
Core monitoring.
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Containment integrity.
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c.
Refueling according to procedure.
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Fuel accountability.
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. Storage of core internals, 1 cads and vessel studs.
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Reactor mode switch locked in refuel.
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Refueling area clernliness.
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Refueling crew licensing requirements.
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Proper vessel water level.
4.
Torus Inspection
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i The inspector accompanied licensee representatives and a consultant on an-inspection of the interior of the torus.
At the conclusion of the inspection the inspector noted that considerable debris (i.e., gloves, boots, polyethylene)was scattered on pipe lines and cable trays between the outer torus catwalk and the basement level.
A licensee representative stated that the area would be c1 caned up and rece'pticles will be provided at clothes change areas.
5.
Procedure to Prevent Inadvertent Criticality Units 1, 2 and 3 The inspector reviewed the remaining open items / of commitments
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made in the licensee's letter (Lee to Keppler) dated January 21,
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1974. No discrepancies were identified.
6.
Jumper Control Log The inspector reviewed the jumper control log books for Unit 1, 2 and 3 and noted that the licensee's revised jumper control procedure is not being used.
It was also noted that this discrepancy was identified as an item of noncompliance during a recent inspection 2/
on Unit 1.
A licensee representative stated that the old procedure has been removed and the revised procedure is available in the jumper log book.
7.
Previous Enforcement Matters The inspector reviewed the licensee's corrective action in response to noncompliance matters identified during the Dresden 2 refueling outage, and noted that:
a.
The master refueling procedure data sheet No. 800-S1 has been revised to insure completion of SRM functional test prior to core alterations.
b.
The licensee now has a master Refueling Nuclear Description provided in accordance with Nuclear Procedure No. 3 (Dated April 1, 1975),
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Inspection Rpt No. 050-249/74-05.
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Inspection Rpt No. 050-010/75-05.
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