IR 05000327/1979066
| ML19308C636 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 12/12/1979 |
| From: | Burnett P, Sauer R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19308C630 | List: |
| References | |
| 50-327-79-66, NUDOCS 8002010034 | |
| Download: ML19308C636 (5) | |
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UNITED STATES 8, 3 NUCLEAR REGULATORY COMMISSION n
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101 MARIETTA $7., N.W.. SUITE 3100
o ATLANTA. GEORGIA 30303
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Report No. 50-327/79-66 Licensee: Tennessee Valley Authority 500A Chestnut Street Chattanooga, Tennessee 37401 Facility Name:
Sequoyah Docket No. 50-327 License No. CPPR-72 Inspection at Sequoyah site near Chattanooga, Tennessee Inspector-/
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Date Signe'd Approved by:
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W T. BtirnsEt, Atting Section Chief, RONS Branch Date Sigofd
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SUMMARY Inspection on November 27-29, 1979 Areas Inspected
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i This routine, unannounced inspection involved 20 inspector-hours on site in the areas of startup test procedure review and followup of previously identified items.
Results r
Of the two areas insnected, no items of noncompliance or deviations were identified.
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.pe 8002010039
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w DETAILS 1.
Persons Contacted Licensee Employees
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- C. E. Cantrell, Assistant Plant Superintendent W. E. Andrews, Quality Assurance Supervisor
- W. II. Kinsey, Results Supervisor
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R. W. Fortenberry, Reactor Engineer
- W. J. Glasser, Powers Manager's Office, Staff Member NRC Resident Inspector
- W.
T. Cottle
- Attended exit interview.
2.
Exit Interview The inspection scope and findings were summarized on November 29, 1979, with those persons idicated in Paragraph I above.
3.
Licensee Action on Previous Inspection Findings Not inspected.
4.
Unresolved Items Unresolved items were not identified during this inspection.
5.
Review of Startup Procedure
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The inspector performed a preliminary in-office examination of the following Unit I startup procedures as to technical content and for conformance to Regulatory Guide 1.68, FSAR Sections 14.1, 15.1, 15.2, 15.3, 15.4, FSAR
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Table 14.1.2 and the TVA Operational Quality Assurance Manual (0QAM), Part II, Section 4.2.
The results of the review were identified to a. licensee representative in a telephone conversation on October 12, 1979. During this inspection the inspector resolved outstanding comments requiring onsite review, and reviewed corrections made and actions taken by the licensee to the various procedures as a result of the inspectors' earlier ctmments. Significant concerns are discussed below.
SU-6.1, Rev. 6, Draft " Initial Core L6ad Procedure" a.
The revision along with Fuel Handling Instruction FH1-7, Rev. 3 " Refueling-Operation (Initial Core Loading)" resolved the 0QAM, Part II, Section 4.2, Paragraph 4.0 requirement for the core loading instructions to specify a minimum crew required to load fuel and crew work time.
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SU-6.2, Rev. 5, Draft " Core Loading Prerequisites" The revision resolves the OQAM, Part II, Section 4.2, Paragraph 4.1 requirement for the fuel load instructions to contain a prerequisite that inspection of fuel. be performed. Fuel llandling Instruction FH1-1,
" Receiving, Inspection, and Storing New Fuel" was added for signature to document satisfactory performance.
c.
SU-6.3, Rev. 2, " Reactor Systems Sampling Prior to and During Core Loading"
The filling of the refueling transfer canal with borated water above the fuel transfer tube nozzle for containment integrity was discussed.
d.
SU-7.2, Rev. 3, " Initial Criticality" l
l The need to add a procedural step to require attaching plotted data to
the completed procedure and the preparer signing and dating the recorded j
data was discussed.
SU-7.6, Rev. 3, "RCCA Pseudo Ejection at Zero Power" e.
The need to cause a slow reactivity transient by boron dilution when restoring the ejected rod was discussed.
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SU-7.7, Rev. 3, Draf t, " Minimum Shutdown Verification" f.
The need to add the recorder QA number on all strip chart recorder traces was discussed.
The need to disconnect the lift coils of all Rod Control Cluster Assemblies of control bank C except the stuck rod was discussed.
g.
SU-8.1, Rev. 2, Draf t " Power Coefficients and Integral Power Defect Measurement" Acceptance criteria values were discussed.
The need to revise the master startup sequence procedure SU-7.1, "NSSS Startup Sequence"; the FSAR startup test performance sequence diagram Figure 14.1-13; and paragraph 4.4.M of the 0QAM, Part II, Section 4.2 (Action on revision taken October 22, 1979) to indicate that SU-8.1 is to be performed at 90% rated power. versus 100% rated power as currently I
indicated. As of this inspection all changes have been made or initiated except for the FSAR Figure 14.1-13 Amendment. This item is considered open (321/79-66-01).
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SU-8.2, Rev. 2, 'RCCA Pseudo Rod Ejection"_.
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The need to revise FSAR Table 14.1-2 to indicate the continuous with-drawal of the most reactive rod at 30% power will be performed without
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borating out was discussed. Action to revise Table 14.1-2 was taken
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on October 22, 1979.
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SU-8.5.1, Rev. 2, Draft "Staplepoint Data Collection and Thermal Power Measurement" The need to address what plant parameters are at equilibrium over a
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specified time intergral to ensure steady state conditions and achieved was discussed.
The following procedures were also reviewed by the inspector.
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SU-7.3.1, Rev. 1, Draft " Nuclear Design Check Tests: Boron Endpoint Determination and Isothermal Temperature Coefficient Measurements" k.
SU-7.3.2, Rev. 0 (Orig), " Nuclear Design Check Tests: Low Power Flux Mapping" 1.
SU-7.5, Rev. 2, " Rod and Boron Worth Measurements During Boron Addition" SU-8.3, Rev. 2, " Static RCCA Drop and RCCA Below Bank Position Measure-m.
ment"
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SU-8.5.3, Rev.1, " Low Power N15 Calibration" SU-8.5.4, Rev.1, " Delta T and IR Extrapolation to 100% Power" o.
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SU-8.6B, Rev. 3, Draf t " Axial Xenon Oscillation" 6.
Followup of Previous Inspection Findings (Closed) Open Item (327/79-50-01): This item addressed the need to a.
revise startup procedure SU-7.2 and SU-6.1 to provide a range of Chi-square values in order to check the consistency of the counting data.
Revision 3 to SU-7.2 and Revision 6, Draft to SU-6.1 were reviewed by the inspector and considered acceptable.
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b.
(Resolved) Resolution to inspector identified item (327/79-16 para-graph 7.a): The need to add a precautionary step in procedure using the reactivity step in procedures using the reactivity computer to limit the measured reactivity insertions to the span of the calibrated range of the computer. Incorporation of paragraph 3.6 to Revision 1, Draf t, SU-7.3.1 was reviewed by the inspector and considered acceptable.
c.
(Resolved) Resolution to inspector' identified item (327/79-16, Para-graph 7.d): The need for the licensee to resolve differences between the requirements in SU-7.3 and paragraph 4.3.E 0QAM, Part II, Section 4.2 on the span of moderator temperature over which the moderator
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temperature coefficient is to be measured at hot zero power. The impector reviewed the revised paragraph 4.3.E of the OQAM dated April 3, 1979, which specifies the moderator temperature reactivity
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coefficient measurement will be performed for various rod configurations.
This change is consistent with the objectives and content of SU-7.3.1 which replaced SU-..
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(Resolved) Resolution to inspector identified item (327/79-16,. para-
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graph 7.f):
The need for the -licensee to specify a frequency of l
checking the operability of the movable income detection system and the conditions required for which a quick check of the voltage-current
saturation plateau is sufficient. The inspector reviewed the draf t
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technical specification change to Section 4.4.3.2, dated October 31, 1979, which specifies a frequency for movable incore detector opera-
bility checks and T1-53 which was written to provide instructions in the use and operation of the movable incore detection system.
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