IR 05000346/1978020
| ML19319B738 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 08/07/1978 |
| From: | Little W, Menning J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML19319B622 | List: |
| References | |
| 50-346-78-20, NUDOCS 8001270193 | |
| Download: ML19319B738 (7) | |
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O U.S. NUCLEAR REGULATORY COMMISSION
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OFFICE OF INSPECTION AND ENFORCEMENT
REGION III
Report No. 50 'i46/78-20 Docket No. 50-346 License No. NPF-3 Licensee: Toledo Edison Company Edison Plaza 300 Madison Avenue Toledo, OH 43652 Facility Name: Davis-Besse Nuclear Power Station, Unit 1 Inspection At: Davis-Besse Site, Oak Harbor, OH
Inspection Condu ted: July 17-19,1978 l
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Inspector:
. E. Menning
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Approved By:
W. S. L1ttle, Chief
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Nuclear Support Fection 2 Inspection Summary Inspection on July 17-19, 1978 (Report No. 50-346/78-20)
Areas Inspected: Routine, unannounced inspection of safety limits, limiting safety system settings, and limiting conditions for operation.
The inspection involved 22.5 inspector-hours onsite by one NRC inspector.
Results: Two apparent items of noncompliance were identified (infraction -
failure to verify proper diesel acceleration during 31-day diesel gen-erator opera.bility demonstrations - Paragraph 2.f, deficiency - failure to properly retain surveillance records - Paragraph 3).
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DETAILS 1.
Persons Contacted
- T. Murray, Station Superintendent
- J. Buck, Operating QA Supervisor P. Carr, Maintenance Engineer
- W. Green, Administrative Coordinator
- J. Lingenf elter, Nuclear and Performance Engineer D. Miller, Operations Engineer
- J. Albert, Babcock and Wilcox Company
- D. Lee, Babcock and Wilcox Company The inspector also contacted other licensee employees, including members of the chemistry and health physics, maintenance, and technical staff.
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- Denotes those attending the exit interview.
2.
Safety Limits, Limiting Safety System Settings, and Limiting Conditions f or Operation
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Plant operations were reviewed for compliance with technical specification requirements for safety limits, limiting safety
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system settings, and limiting conditions for operation.
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resiew focused on the plant systems listed below and included j
discussions with facility representatives, direct observation of plant activities, review of operating records and procedures, and examination of surveillance test records.
Reactivity Control and Power Distribution a.
The inspector reviewed shif t check data obtained per ST 5099.01 for the month of December 1977, and verified that recorded data was consistent with the following
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technical apecification requirements:
(1) Agreement between axial power shaping rod individual position indications and the group average height (TS 3.1. 3. 2).
(2) Agreement between the absolute and relative position indications of the safety, regulating, and axial power shaping rods (TS 3.1.3.3).
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(3) Safety r. positions (TS 3.1.3.5).
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b (4) Axial power imbalance (TS 3.2.1).
(5) Regulating rod positions (TS 3.1.3.6).
One shift check sheet (ST 5099.01) for December 4, 1977 and another for December 22, 1977 could not be located for the inspector's review.
(See paragraph 3 - Missing Surveillance Records).
The inspector also reviewed the records of shutdown margin verifications performed during December 1977, in accordance with ST 1103.15 and verified that the requirements of TS 4.1.1.1.1.e were satisfied.
b.
Instrumentation The inspector reviewed ST 5030.02, " Reactor Protection System Monthly Checks," and verified that the required setpoints for reactor coolant system high temperature, high pressure, and low pressure were consistent with the technical specification requirements. In addition, the inspector reviewed test data obtained per ST 5030.02 during the period February 3, 1978 to March 30, 1978 and verified that the recorded values for the
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reactor coolant system high temperature, high pressure, and (,,,/
low pressure setpoints were consistent with the procedural and technical specification requirements.
The inspector reviewed ST 5036.01, " Remote Shutdown Monitoring Instrumentation Monthly Checks," and verified that the procedural requirements were consistent with TS 4.3.3.5.
In addition, the inspector reviewed the test data obtained per ST 5036.01 during the period July 13, 1977 to April 17, 1978 and verified that the test results were consistent with procedural and technical specification requirements.
c.
Reactor Coolant System The inspector reviewed pressurizer level check data obtained per ST 5099.01 during the month of December 1977, and veri-fied that the recorded values were consistent with TS 3.4.4.
One shift check sheet (ST 5099.01) for December 4, 1977 and another for December 22, 1977 could not be located for the inspector's review.
(See paragraph 3 - Missing Surveillance Records).
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In addition, the insnector reviewed the purification demin-
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eralizer inlet sample data for November 1977, and February 1978, D-3-
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Y ps and verifi, that the dissolved oxygen, C1, and F concen-trationr sere consistent with the requirements of TS Table 3.4-1.
d.
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The inspector reviewed core flood tank volume, nitrogen cover pressure, ar:1 isolation valve check data obtained per ST 5099.01 daring the month of December 1977, and virified that the recorded data (with one exception) were consistent with
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The inspector noted that nitrogen cover pressures between 280 and 290 psig were recorded on a shift check sheet (ST 5099.01) on December 10, 1977. Although these values are well below the minimum allowable technical specification value of 575 psig, the data was signed off by all reviewers as satisfactory. This discrepancy was brought to the attention of a licensee representative who subsequently investigated the matter. The licensee eventually concluded that the nitrogen pressures had probably been incorrectly recorded since no evidence could be found to confirm the low pressures. The licensee agreed to attach an explanatory memo to the involved surveillance record.
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One shift check sheet (ST 5099.01) for December 4, 1977 and another for December 22, 1977 could not be located for the y,/
inspector's review.
(See paragraph 3 - Missing Surveillance Records).
Core flood tank boron concentration 31-day verification data obtained per ST 5050.01 were reviewed for the period June 22, l
1977 to June 26, 1978 and found to be consistent with the requirements of TS 3.5.1.
In addition, the inspector reviewed borated water storage tank concentration and level 7-day veri-fication data obtained per ST 5052.01 for the period April 25, 1978 to June 27, 1978 and verified that the recorded values were consistent with TS 3.5.4.
Borated water storage tank
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daily temperature check data obtained per ST 5099.02 were reviewed for the month of December 1977 and verified to be consistent with the requirements of TS 3.5.4.
e.
Containment i
The inspector reviewed primary containment penetration 31-day status verification data obtained per ST 5060.01 for the period between June 30, 1977 and June 25, 1978.
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Although all reviewed data were found to be consistent
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,V with the requirements of TS 4.6.1.1.a. the licensee could not locate the record for the surveillance performed in February 1978.
(See paragraph 3 - Missing Surveillance Records).
Containment internal pressure 12-hour check data obtained per ST 5099.01 during the month of December 1977, were reviewed and found to be consistent with the requirements of TS 3.6.1.4.
One shift check sheet (ST 5099.01) for December 4, 1977 and another for December 22, 1977 could not be located for the inspector's review.
(See paragraph 3 - Missing Surveillance Records).
Containment air temperature daily check data obtained per ST 5099.02 during the month of December 1977, were reviewed and found to be consistent with TS 3.6.1.5.
In addition, the inspector reviewed the Containment Direct Path Log for the period of January and February 1978, and verified that the requirements of TS 4.6.1.7 were satisfied.
The inspector reviewed hydrogen analyzer quarterly calibration data obtained per ST 5065.01 during the period July 14, 1977 (x to April 14, 1978 and verified that the requirements of TS (
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4.6.4.1 were satisfied.
Containment recirculation system
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quarterly operability test data obtained per ST 5065.06 during the period July 7, 1977 to July 3, 1978 were reviewed. Although reviewed test data were found to be consistent with TS 4.6.4.2, the test record for Fan 1-1 testing on February 23, 1978 could not be located for the inspector's review.
(See paragraph 3 -
Missing Surveillance Records).
Containment hydrogen dilution system quarterly operability test data obtained per ST 5065.02 during the period July 28, 1977 to April 26, 1978 were reviewed and found to be consis-tent with the requirements of TS 4.6.4.3.
f.
Electrical Diesel generator 31-day operability test data obtained per ST 5081.01 during the period January 9, 1978 to June 28, 1978 were reviewed. The inspector noted that ST 5081.01 did not include a requirement to verify diesel acceleration from the ambient condition to at least 900 rpm in 10 seconds or less as required by TS 4.8.1.1.2.a.4.
In initial dis-cussions on July 19, 1978, cognizant licensee personnel could
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not immediately explain why ST 5081.01 did not include veri-
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fication of proper diesel acceleration and they stated that m
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t the verification might be included in another surveillance During the exit interview a licensee representative test.
stated that the plant staf f would continue to investigate the inspector's concerns about the diesel acceleration veri-5081.01 to fication and committed to expeditiously revise ST include the verification required by TS 4.8.1.1.2.a.4 pending
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The licensee 'tepresentative also resolution of the concerns.
stateo that the verification of proper diesel acceleration had recently been accomplished (in June 1978) as part of the 18-month SFAS integrated test.
In a telephone conversation with the inspector on July 21, 1978 a licensee represent'ative I
stated that (1) investigation revealed that verification of proper diesel acceleration had a one time been included in but was erroneously celeted in a procedure revision ST 5081.01 in July 1976; (2) verification of proper diesel acceleration as required by TS 4.8.1.1.2.a.4 had not been performed as part of another 31-day surveillance test; (3) ST 5081.01 had been revised to reinsert the verification of proper diesel accel-eration; and (4) satisf actory testing of the diesel generators in accordance with the newly revised ST 5081.01 had been completed.
Failure to verify diesel acceleration from ambient condition to
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at least 900 rpm in 10 seconds or less as part of the 31-day
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diesel generator operability testing is considered to be an ( ~s item of noncompliance against the Technical Specifications I
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Section 4.8.1.1.2.a.
A licensee representative was advised
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of this finding during a telephone conversation with the inspector on July 21, 1978.
The inspector reviewed weekly surveillance data for station battery IP obtained per ST 5084.01 during the period January 3, 1978 to June 21, 1978 and verified that the requirements of TS 4.8.2.3.2 were satisfied.
3.
Missing Surveillance Records The licensee was unable to locate one shift check sheet (ST 5099.01)
for December 4, 1977 and another for December 22, 1977. A review of the Unit Log revealed that required shif t checks were performed per ST 5099.01 on these dates.
In addition, records of containnent 5065.06 on February 23, recirculation system testing performed per ST 1978 and of the containment integrity verification performed per ST 5060.01 during February 1978, could not be located for the The licensee's surveillance tracking records inspector's review.
In indicated that these two items had been performed as required.
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the exit interview a licensee representative stated that efforts In a to locate the missing surveillance records would continue.
telephone conversation with the inspector on July 24, 1978, a
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licensee representative stated that the missing surveillance records could not be found and that ef forts to find them had been terminated.
Failure to retain these four surveillance records is conside ed to be an item of noncompliance against TS Section 6.10.1 which requires that records of technical specification surveillance activities be retained for five years. The licensee representative was advised of this finding during the telephone conversation on July 24, 1978.
During the exit interview the inspector stated that surveillance reviewers appeared to be retaining records for excessively long periods of time and that this situation could adversely impact on the licensee's record control efforts. As an example, the inspector related that he attempted to review the one hundred and twenty four surveillance records generated per ST 5099.01 and ST 5099.02 during December 1977. Twenty one of these records were found to still be in the review process, and consequent',; not in the licensee's central files on July 17, 1978.
4.
Exit Interview The inspector met with licensee representatives (denoted in paragraph 1) at the conclusion o-the inspection on July 19, 1978.
The The inspector summarized the scope and findings of the inspection.
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principal NRC facility inspector, T. N. Tambling, also attended the exit interview.
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