IR 05000395/1985045

Insp Rept 50-395/85-45 on 851210-16.No Violation or Deviation Noted.Major Areas Inspected:Startup Tests & Site Witnessing

ML20136J155
Person / Time
Site:	Summer
Issue date:	01/06/1986
From:	Burnett P, Jape F NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20136J147	List: IR 05000395/1985045 ML20136J143
References
50-395-85-45, NUDOCS 8601130229
Download: ML20136J155 (6)

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UNITE 3 STATES km R892,D o NUCLEAR REGULATORY COMMISSION

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Report No.: 50-395/85-45 Licensee: South Carolina Electric and Gas Company

, . Columbia, SC 29218 Docket No.: 50-395 License No.: NPF-12 Facility Name: V. C. Sumer

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Inspection' Conducted: Dec er 10-16, 1985 Inspector: .

MmR / -f4 PM. Bufn' tt ' ~ ~ ~ Date Signed Approved by: /l M F. Jape, Section Chief M/

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(/ Date Signed Engineering Branch Division of Reactor Safety

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SUMMARY Scope: This routine, unannounced inspection entailed 40 inspector-hours on site witnessing and reviewing post-refueling startup tests. =

Results: No violations or deviations were identified.

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8601130229 860107 PDR ADOCM 05000395 0 PDR

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REPORT DETAILS 1. Persons Contacted Licensee Employees 0. S. Bradham, Director, Nuclear Plant Operations

• J. G. Connelly, Deputy Director, Operations and Maintenance

• B. G. Croley, Group Manager Technical and Support Services K. W. Woodward, Manager Operations

• M. N. Browne, Manager, Technical Support

• G. A. Loignon, Associate Manager, Performance and Results

• A. R. Koon, Associate Manager, Regulatory Compliance

• S. F. Fipps, ISEG Engineer H. Donnelly, Licensing Engineer

• R. M. Fowlkes, Regulatory Interface Engineer D.

Deardorff,

Reactor Engineer B. R. Devendorf, Reactor Engineer /STA W. Haltiwanger, Reactor Engineer Other licensee employees contacted included shift technical advisors, shift supervisors, test engineers, operators, instrument technicians, and office personnel.

NRC Resident Inspectors

• R. L. Prevatte, Senior Resident Inspector

• P. C. Hopkins, Resident Inspector

• Attended Exit Interview 2. Exit Interview The inspection scope and findings were summarized on Decenber 16, 1985, with those persons indicated in paragraph 1 above. The inspector described the areas inspected and discussed in detail the inspection findings. No dissenting connents were received from the licensee, and the following commitments were confirmed by management: .

Inspector followup item 395/85-45-01: In the course of the two-year cycle procedure review and upgrade program, the surveillance and test procedures discussed here will be revised to provide signoffs for each procedure step (paragraph 5.d).

Inspector followup item 395/85-45-02: The use of a test log will be instituted for startup test programs (paragraph 5.d).

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Inspector followup item 395/85-45-03: Additional guidance will be placed in rod-worth and temperature measurement pecedures to assure scaling and spanning of chart traces provides the largest practical trace for graphical analysis (paragraph 5.d).

Proprietary material was reviewed during chis inspection, but is not included in this report.

3. Licensee Action on Previous Inspection Findings (Closed) Violation 395/85-15-02: Failure to implement the required compen-satory action for an inoperable power-range nuclear flux channel. In a letter dated June 21, 1985, the licensee agreed with the violation, and in an attachment to the letter committed to completing corrective action by July 31, 1985. Surveillance test procedure (STP) 310.005(Revision 5),NIS Power Range (N41) Calibration, underwent changes B and C on April 3,1985 and May 11, 1985, respectively. Change B added step 3.14 to implement the requirement to perform STP-108.001, Quadrant Power Tilt Ratio, every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> with N41 out of service. Change C revised the procedure step (3.14)

to conform to the requirements of Technical Specifications and added a sign off block in attachment I. Similar changes were made to the calibration procedures for channels N42, N43, and N44 in the same time frame. The corrective action is judged to be both adequate and timelj.

(Closed) Violation 395/85-12-01: Failure to follow procedura during startup on February 28, 1985. The licensee acknowledged the violation and proposed acceptable corrective action in an attachment to a letter dated May 3, 1985.

Completion of the corrective action has been confirmed.

(Closed) Violation 395/85-12-02: Procedures were inadequate to estimate criticality within reasonable uncertainty. The licensee acknowledged the violation and proposed acceptable corrective action in an attachment to a letter dated May 3, 1985. Implementation of acceptability revised procedures has been confirmed.

4. Unresolved Items Unresolved items were not identified during this inspection.

5. Post-refuelingStartupTests(72700,61708,61710)

a. The following procedures were reviewed prior to perforriance:

REP-107.003 (Revision 0), Beginning of Cycle Dilution to Criticality, REP-107.001 (Revision 1), Controlling Procedure for Refueling and Refueling Startup Testing, REP-107.008(Revision 0),BoronEndpointMeasurement,

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STP-210.002 (Revision 0), Isothermal Temperature Coefficient Measure-ment, and REP-103.001 (Revision 1), Control Rod Worth Measurement. A draft Westinghouse report, "Startup Physics Package for The V. C. Summer Nuclear Power Plant, Cycle 3 (October 1985)" was reviewed in concert with these procedures. At the end of the review it was concluded that the proposed test program was technically sound and essentially similar to programs recently found acceptable at other PWRs.

Administrative 1y, the program could be stronger. Rather than provide for sign-off of procedure steps within the body of the procedure, separate sign-off sheets are attachments to the procedures. That practice is not inherently unacceptable. However, in these procedures most sign-offs cover multiple steps. For example, a sign-off in the attachment for step 7.5 might, in fact, be for steps 7.5.1 to 7.5.12 inclusive. Those steps might not necessarily be performed as a continuing action, occurring over a short period of time or under the

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purview of a single individual, b. Performance of the following procedures was witnessed in whole or in part:

STP-208.001 (Revision 2), Shutdown and Control Rod Drop Test. All rod drop times were well within the Technical Specification limit.

. REP-107.003, Beginning of Cycle Dilution to Criticality. Criticality

was achieved in a well-controlled manner. After termination of dilution, the coolant continued to mix with control bank D at 160 steps. Once repeated baron samples demonstrated a constant value of 1799 ppmB, precisely as predicted for the amount of dilution water injected, bank D was moved to 163 steps to confirm divergence.

Subsequently, the all-rods-out (AR0) critical boron concentration was measured to be 1828 ppm in excellent agreement with the predicted value of 1823 ppm.

REP-107.008, Baron Endpoint Measurement, for the all rods out configuration.

REP-107.009, Low Power Flux Mapping.

REP-103.001, Control Rod Worth Measurement, including part of the measurement of control bank B by baron dilution, and part of the measurement of control bank C by comparison with control bank B. The inspector noted that the scaling and spanning of the reactivity computer chart recorder was such that only a small portion of the available space was used to record the trace. Since the trace is analyzed or solved graphically, there is more uncertainty in the results than had different scaling and greater reactivity spans led to greater slopes and spans.

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c. The following completed test procedures were reviewed:

REP-107.003, Beginning of Cycle Dilution to Criticality. Several marginal notes were observed in the procedure, which appeared to have been entered by the test engineers to compensate either for the lack of detail in the sign-off sheets or the lack of a test log.

REP-107.008, Boron Endpoint Measurement, for the all-rods-out configuration.

STP-210.002, Isothermal Temperature Coefficient Measurecent, for the all-rods-out configuration was negative, but the corresponding moderator temperature. coefficient was approximately 1 pcm/F positive.

The licensee promptly initiated action to remeasure the moderator temperature coefficient under conditions certain to produce a negative coefficient. From the two measured coefficients, curves of boron concentration and rod withdrawal limits will be established to assure the moderator coefficient is negative once physics testing is completed.

d. Based on the above inspection activities, the inspector held extensive discussions with the licensee staff and obtained the following commitments to be tracked as inspector followup items:

Inspector followup item 395/85-45-01: In the course of the two-year cycle procedure review and upgrade program, the surveillance and test procedures discussed here will be revised to provide sign-offs for each procedure step.

Inspector followup item 395/85-45-02: The use of a test log will be instituted for startup test programs.

Inspector followup item 395/85-45-03: Additional guidance will be placed in rod-worth and temperature measurement procedures to assure scaling and spanning of chart traces provide the largest practical trace for graphical analysis.

6. Previous Outstanding Items (92701)

(Closed) Inspector followup item 395/82-28-02: Implementation of non-destructive examination procedures for special lifting devices. By letter dated January 25, 1985, the licensee submitted their final response to NUREG-0612, Control of Heavy Loads at Nuclear Power Plants. On page 4-5 of the response, the licensee described the inspection practice to be applied to the reactor vessel head lift rig and the reactor vessel internals lift rig in lieu of the requirement of ANSI N14.6 Section 5.3. Current plant procedures, MMP-500.006 and MMP-500.005, implement the stated practice. This item is closed.

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(Closed) Inspector followup item 395/82-52-03: Evaluate alternative alternate dilute modes for use with new cores to avoid overshooting initial criticality. .The licensee has instituted administrative controls on dilution rate in _ REP-107.003, Beginning 'of Cycle Dilution to Criticality.

These controls were observed to work well during this inspection. This item is closed.

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