IR 05000312/1979004
| ML19270G626 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 04/24/1979 |
| From: | Andrea Johnson, Shafer W, Witt K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML19270G627 | List: |
| References | |
| 50-312-79-04, 50-312-79-4, NUDOCS 7906140205 | |
| Download: ML19270G626 (5) | |
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U.S. NUCLEAR REGULATORY CO.T!ISSION
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OFFICE OF INSPECTION AND ENFORCE!!ENT
REGION V
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Report No.:
50-312/79-04 Docket No.:
50-312 License No.: DPR-54 Licensee:
Sacramento !!unicipal Utility District P. O.
Box 15830 i
Sacramento, CA 95813
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Facility Name: Rancho Seco Inspection At: Rancho Seco Inspection Conducted:
Feburary 26 - 11 arch 2,1979 l0.D.'Sha")
Inspector:
W. D. Sha er, Inspector Specialist d,2-7h Performance Appraisal Branch, IE
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Accompanying Personnel:
.J i on actor In pector R
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G. W. Johnston, Reactor
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Inspector, RV
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Approved By: Kermit Whitt, Chief
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Performance Appraisal Branch, IE
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Inspection Sunmary j
l Inspection on February 26 - !! arch 2, 1979 (Report No. 50-312/79-04)
Areas Inspected:
Routine, announced inspection to review the licensee's
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surveillance test program during the time period of October 1977 - October 1978. The inspectioninvolved 32 inspector-hours onsite by one Performance Appraisal Branch Inspector.
Results:
No apparent items of noncompliance or deviations were identified.
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DETAILS i
i 1.
Persons Contacted
- R.
J. Rodriguez, Nuclear Operations >bnager
- P. Oubre, Plant Superintendent
- R.
Colombo, Technical Assistant
- W.
Ford, Nuclear Operations Supervisor
- G.
Coward, Plant Mechanical Engineer The inspector also talked with and interviewed several other licensee employees from the technical and engineering staf f.
- Denotes those present at the exit interview.
2.
Surveillance Test Program Review The Performance Appraisal Branch objective is to conduct an indepth, ; narrowly scoped review of the licensee's surveillance program in order to provide information for the appraisal of licensee's performance from a national perspective.
The nature and magnitude of the findings did not indicate a need to investigate other areas.
Therefore the entire inspection was performed within the planned scope.
In support of this objective the inspector conducted a review of the licensee's sarveillance test program to determine that the Technical Specifications surveillance tests performed by the licensee were covered by properly approved procedures; that the procedures included prerequisites, appropriate identification of calibrated instrumentation acceptance criteria, and operational checks prior to r(turning the equipment to service. The inspector also verified for those tests selected, that test results were properly reviewed and in conformance with the Technical Specifica-tions and procedural requirements.
The Technical Specification tests as identified in the following table, were reviewed during the inspection.
Cooments regarding specific surveillance tests reviewed are referenced by Paragraph in the Findings Section.
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Tech Spec No.
Procedure No.
Surveillance Requirement Samples Findings _ Cj TS Table 4.1-1 SP 200.08A Power Range Channel Test
Clear c;)
(Item 4)
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(NJ TS Table 4.1-1 SP 200.08A Reactor Coolant Temperature Channel Tests
Clear CNJ (Item 7)
TS Table 4.1-1 SP 200.08A Pump / Flux Comparator Test
Clear (Item 10)
Il08-A TS Table 4.1-1 SP 200.08A CRD Trip Breaker
Clcar (Item 13)
Il08-A TS Table 4.1-1 SP 200.09 High Pressure injection, Emergency Building 132 Clcar
(Item 16)
I-200A Cooling and Building Isolation Digital Logic
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Channels Test i
TS Table 4.1-1 SP 200.02 Pressurizer Level Channels Test 200 Clear (Item 29)
TS Table 4.1-2 SP 208.02 Control Rod Movement 216 Clear (Item 2)
TS Table 4.1-2 SP 207.03 Pressurizer Code Safety Valve Sctpoint
Clear (Item 3)
TS Table 4.1-2 SP 207.04A & B Daily and Weekly Reactor Coolant System 450 Clear (Item 7)
Leakage Tests TS Table 4.1-3 SP 202.01 Reactor Coolant Sampling 104 Clear (Item 1)
TS Tabic 4.1-3 SP 202.02 BWST Boron Concentration
Clear (Item 2)
TS Table 4.1-3 SP 202.03 Core Flooding Water Tank Water Sample
Clear hsTabic4.1-3 SP 202.06 Concentrated Boric Acid Tank Tests 104 Clear (Item 6)
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Number of Tech Spec No.
Procedure NO-Surveillance Requirement Samples Findings
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N TS 4.4.1.3 SP 205.07A & B Isolation Valve Functional Tests
Clear (NJ f~{
TS 4.5.1.2.A SP 203.02A, B, & C HPI "akeup and Decay Heat Removal Pumps
Clear N
TS 4.5.1.2.B SP 203.06A Safety Feature Valves in ECCS Valve
See Para. a csa Operability Test TS 4.5.1.2.C SP 203.02A, B, & C Nuclear Service Cooling and Raw Water
Clear System Tests TS 4.5.2.2.A SP 204.03A & B Reactor Building Spray Pumps
Clear TS 4.5.2.2.B SP 203.06A, B, & C Safety Feature Valves in the Reactor Build-
See Para. a SP 203.02A, B, & C ing Spray, Reactor Building Emergency Cool-ing System and Nuclear Service Water System TS 4.6.1 SP 206.03A & B Diesel Generator and Associated Equipment
Clear Operability Test
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TS 4.6.4 SP 206.04 125 VDC Batteries 204 Clear
TS 4.6.5.A SP 206.03A & B Fuel Transfer Pump Operability Test
Clear TS 4.6.5.B SP 206.03A & 3 Diesel Fuel Oil Quantity
Control Rod Program Verification 276 Clear
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Within the areas inspected the following concerns were identified:
During the review of the licensee's program for determination a.
I of operability of safety feature system isolation valves, the inspector noted that the present Technical Specification requirements for these valves is the proper stroking for i
determination of operability.
llowever, the licensee also requires that these valves to be timed, but does not in all j
cases identify an acceptable time limit for these valves l
(reference surveillance procedure 203.06A).
Further review showed the licensee in preparation for compliance with the
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ISI valve and pump operability test as required by ASME Section 11.
The commitment to comply with the requiremencs of the ISI program, as a result of an extension granted by NRR, will not become effective until October, 1979. This area will be reviewed by the Region V personnel after the
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program has been fully implemented.
l 3.
Exit Interview The inspector met with licensee representatives (denoted in Paragraph 1) at the conclusion of the inspection on March 2, 1979 and summarized the findings and scope of the inspection.
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