IR 05000483/1991009
| ML20024G905 | |
| Person / Time | |
|---|---|
| Site: | Callaway  |
| Issue date: | 04/25/1991 |
| From: | Gardner R, Neisler J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20024G898 | List: |
| References | |
| 50-483-91-09, 50-483-91-9, NUDOCS 9105020070 | |
| Download: ML20024G905 (4) | |
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NUCLEAR REGULATORY COMMISSION ~
REGION III
l Report No.:
50-483/91009(DRS)
Docket No.:
50-483 License No.
NPF-30-Licensee:
Union Electric Company Post Office Box 149 - Mail Code-400 St. Louis, MO 63166-Facility Name:
Callaway-Nuclear Power Plant - Unit'1
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Inspection At:
Steedman, MO-65077 Inspection Conducted:
April 8-12,.1991 Inspector:
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/J( M eisler Dave h
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-Approved By:
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R.-N.
Gardner, Chief Date Plant Systems Section Incoection Summary Inspection on April 8-12, 1991-(Recort No. 50-483/91009(DRS))
Areas Inspected:. Routine announced-inspection-of the licencee's implementation of_the ATWS Rule _(10 CFR 50.62),' including-the-
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design, installation, and testing-of-the ATWS mitigation system (25020) (MPA-A-20).
Results:
No violations or deviations were identified.
Based on this inspection, the-inspector determined-that_the licensee has adequately implemented tho' requirements _of 10--CFR 50.62-'and-
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The-inspector' considered the licensee's performance in the areas ~of ATWS-construction, maintenance and-training to be excellent.
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9105020070 910425
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PDR ADOCM 050004B3-G
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DETA_ILS
1.
Persons Contacted Union Electric Comoany (UE)
G.
Randolph, Vice President, Nuclear J.
Blosser, Manager, Callaway Plant
- J.
Laux, Manager, Quality: Assurance
- L.
Kanuckel, Supervisory Engineer,LQuality Assurance
- E.
Erbschloe, Nuclear Scientist, I&C
- S.
Petzel, Quality Assuranco Engineer
- J.
McGraw, Superintendent, Design Control
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C. Slizewski, Supervisory Engineer, Quality Assurance W.-Campbell, Manager, Nuclear Engineering J.
Moore, Design Engineer, ATWS U.
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Nuclear Reaulatory Commission (NRC)
- B.-Bartlett, Senior Resident Inspector
- Denotes those persons attending the exit interview on
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April 12, 1991.
2.
ATWS TI 2500/20 (MPA-A-20)
The inspector reviewed the licensee's implementation of-the ATWS Rule, 10 CFR 50.62, and the design and installation of the ATWS Mitigation System Actuation Circuitry (AMSAC).
a.
pesian Enaineerina (1)
Review of drawings,. design.submittals and the AMSAC modification confirmed that the Callaway AMSAC design and its-implementation did not compromise the safety features of-the existing
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safety-related reactor protection systems.
Walkdown of the AMSAC components:and system supported this conclusion.
(2)
The Callaway:AMSAC-is designed to trip the main turbine land start the auxiliary feedwater pumps on low water levels in the steam generators.
-The AMSAC actuates when 3 out of 4 steam generator narrow range-levels fall below the setpoint_for more than 25 seconds and turbine:-impulse pressure is above 40% power.
(3)
Review of the AMSAC modification. package and
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walkdown of the-systems. indicated that the design endorsed by the NRR Safety-Evaluation Report (SER)
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had_been properly _ implemented.- Design diversity met SER-requirements.
The AMSAC is equipped with adequate operating and maintenance bypasses and is testable at power.
(4)
The AMSAC is designed so that once actuated, after low levels are present in 3 of 4 steam generators for 25 seconds, the mitigating action will go to completion.
There is no manual reset capability once AMSAC actuation is initiated.
Automatic reset is accomplished-after the C-20 permissive changes state about 120 seconds after plant power decreases below 40 percent, b.
' Installation and Procurement (1)
The inspector reviewed the quality assurance program and related documentation and determined that procurement controls, vendor inspections-and warehouse receipt inspections were adequate.
(2)
.The inspector verified-by review-of quality assurance surveillances-and. quality control inspection reports that the required. inspections and surveillances were performed during installation and preoperational testing of the AMSAC.
Deviations and nonconformances. identified were promptly and' adequately corrected.
(3)
Operating and calibration procedures had been revised toLreflect the AMSACEmodification requirements.
Surveillance-and testing
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requirements based on the-manufacturer's recommendations had been developed and implemented.
Training for operators and instrumentation and control' technicians-had been-l accomplished.
(4)
The inspector determined that'the latest _
installation specifications and: drawings had beeni
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used for the AMSAC installation.. The AMSAC cabinet was: seismically qualified and plug-welded to a previously installed base in the control.
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room.
Apparently, the cabinet base was:not level which resulted in the AMSAC cabinet _being installed out of_ plumb.
.The condition was recognized by the_ installers who receivedL y
permission from the_ cognizant design engineer to-
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install the cabinet at an angle. ~There was no documented evidence that the design engineer had considered whether installation'of the AMSAC cabinet out of plumb would impact the--seismic
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qualification of the cabinet, k'hile the inspector
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-was on site, the licensee performed the necessary calculation to prove the seismic integrity of the AMSAC cabinet in its as-installed configuration.
(5)
Review of the modification installation package verified that the AMSAC was installed using suitable equipment in accordance with established procedures and that proper housekeeping, radiological, and fire protection: controls were employed, (6). During the walkdown,.the-inspector verified that the plant's' physical separation criteria-for.
maintaining electrical independence between redundant safety related circuits and between
- safety and nonsafety related circuits were satisfied.
The inspector also verified that qualified isolation devices were used to interface
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between the'nonsafety-related portions of the ATWS systems and existing safety related protection
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systems as required by the ATWS rule.
(7)
The licensee's quality assurance _ activities for the ATWS program met the requirements of Generic Letter 85-06.
Observations and discussions with personnel involved with the ATWS program confirmed their knowledge and capability of implementing the-ATWS program.
Generic Letter 85-06 and TI 2500/20 are considered to be closed at Callaway Unit 1.
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3.
Exit Interview The inspector met with licensee-representatives (denoted in-Paragraph 1) at the conclusion of the inspection and summarized the mcope and findings of the' inspection.
The inspector-discussed the likely informational content of.the inspection report with regard to documents or processes reviewed by.the inspector during the' inspection.
'The licensee did not-identify any-such documents or processes as proprietary.
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