ML18139A459
| ML18139A459 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 07/18/1980 |
| From: | Sylvia B VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| 630, NUDOCS 8007210453 | |
| Download: ML18139A459 (5) | |
Text
VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND,VIHGINIA. 23261 July 18, 1980 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation Attention:
Mr. Steven A. Varga, Chief Operating Reactors Branch 1 Division of Licensing U. S. Nuclear Regulatory Commission Washington, D. C.
20555
Dear Mr. Denton:
INTEGRATED STARTUP TEST PROGRAM SURRY POWER STATION UNIT 2 Serial No. 630 NO/JLW/FHT:smv Docket No. 50-281 License No. DPR-37 We are submitting, for your review, an update of our letter dated August 13, 1979, regarding our Integrated Startup Test Program.
It addresses the inspec-tion and testing of Surry Power Station Unit No. 2 after the Steam Generator Repair Program and the subsequent return to full power operation.
As expected, during a
- program of this magnitude, many repair related delays have been encountered which caused the sequencing of certain tests to be altered.
How-ever, the program still follows the intent of Regulatory Guide 1.68, Revision 2,
- August, 1978, "Preoperational and Initial Startup Test Programs for Water Cooled Power Reactors".
It is the intent of this letter to explain the resequencing of certain tests that have taken place in the Preoperational Phase of testing and the additional controls implemented for the "Integrated Startup Test Program" to govern the Startup Phase of testing.
The tests in the Preoperational Test Phase as submitted in August, 1979, were designed "to provide assurance that components and subsystems of new, modified and original systems function safely within established design criteria". All new and modified systems were fully tested prior to being placed in service.
Original systems that were not affected by design change may or may not have had their functional checks performed during this phase.
In some cases, the actual performance checks of the original systems will be verified during the Startup Phase as this is more appropriate for verifying actual system condi-tions.
This approach is taken on original systems to ensure satisfactory performance.
Any component that was disconnected from original systems during this outage was individually tested according to approved procedures.
As of June 4, 1980, the remainder of the Integrated Startup Test Program will be governed by the newly developed "Startup Matrix".
This "Startup Matrix" is approved by the Surry Power Station Nuclear Safety and Operating Committee
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VIRGINIA ELECTRIC AND POWER COMPANY TO Mr. Harold R. Denton, Director (SNSOC).
It is specifically controlled by the Superintendent of Operations.
The Superintendent of Operations (or his designee) has the sole authority to approve deviations to the Startup Matrix prior to the implementation of the deviation.
The SNSOC will review these deviations in accordance with the Nuclear Station Quality Assurance Manual.
The Startup Matrix is available at the site for review and has been provided to the resident inspector.
Preoperational Test Phase The sequencing of testing during the Preoperational Test Phase was altered from that which was originally set forth in Appendix B of our August 13, 1979, letter.
This was deemed necessary in order to efficiently maintain a comple-tion schedule for this outage.
However, changes were evaluated to insure that the public health and safety was not endangered by these alterations.
Tests and events remained within the Technical Specification requirements for Surry Unit No. 2.
The resequencing of tests was within the scope of our original program which stated as follows:
"The actual sequence of individual tests is formulated prior to performance of the tests considering equipment availability and is maintained on an Integrated Startup Test Schedule."
However, daily Planalog sessions were used in place of the Integrated Startup Test Schedule as the means for tracking the detailed tests.
Weekly progress meetings were the means of tracking the overall outage schedule.
The following is a description and reasons for resequencing certain tests under the Preoperational Test ~hase from that which was originally submitted in Appendix B "List of Major Preoperational Tests and Checks" of our August 13, 1979, letter.
Only the testing that was resequenced will be discussed.
- 1.
Appendix B, VI-Auxiliary Systems, item /fl, Residual Heat Removal System Test The residual Heat Removal System essentially remained in service except for maintenance work to the pumps and the addition of an expansion loop to the recirculation line.
Normal system O.P.'s and P. T. 's were used to run the system in support of various pre-core loading tests.
- 2.
Appendix B, VI-Auxiliary Systems, item #2, Containment Instrument Air System The newly designed Containment Instrument Air System was not fully erected prior to core loading.
Containment Instrument Air was main-tained through the normal backup supply from the Turbine Building.
The new Containment Instrument Air System will be in full operation prior to setting final Containment Integrity for Hot Functional Testing.
- 3.
Appendix B, VI-Auxiliary Systems, item #3, Shield Tank Cooling System The Neutron Shield Tank Cooling System's final operational check is being delayed until Hot Functional Testing in order to fully check out the operational data of the natural circulation cooling with the
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VIRGINIA ELECTRIC Al',D POWER COMPANY TO Mr. Harold R. Denton, Director Reactor Coolant System at temperature.
Individual components that were disconnected during the Steam Generator Replacement Project were individually tested according to station approved procedures.
The performance check will be done under the Component Cooling Per-formance Procedure.
- 4.
Appendix B, VIII-Containment Systems, item fll, Reactor Con.tainment Tests The final Reactor Containment Integrated Leak Rate Test (Type A) was postponed until after core loading instead of prior to core loading in order to have all components that penetrate the containment pressure boundary in completed readiness to support this test.
Preliminary Type A tests were* performed prior to core loading in order to identify problems with systems and components.
Refueling containment integrity was maintained during core loading in a manner similar to previous refueling outages.
The Integrated Leak Rate Test was successfully completed after refueling with systems aligned to, or as near as practical to, accident conditions.
A detailed report of this test is being written and will be submitted in accordance with Appendix J to 10CFR50.
- 5.
Appendix B, IX-Gaseous Radioactivity Removal System This system was erroneously identified as being tested in the Pre-operational Phase and the Startup Phase.
However, this is common to both Surry Unit Nos. 1 and 2, and has remained in service in support of Unit No. 2 operations.
No special testing will be per-formed on this system other than normal operations and periodic testing.
- 6.
Appendix B, X-Emergency Core Cooling System, item #1, High Pressure Safety Injection Tests The High Pressure Safety Injection Tests will officially be performed during Hot Functional Testing.
The Charging System was. actually used during many of the pre-fuel loading tests and normal operations under O.P.'s and P.T.'s.
Additional performance tests, other than O.P.'s and P. T. 's, will be accomplished during Hot Functionals when the testing can be performed at actual plant conditions.
This approach was taken since no major rework was performed on this system.
Com-ponents that were disconnected during the Steam Generator Replacement Project were individually tested under station approved procedures.
Startup Test Phase The testing in the Startup Test Phase is essentially the same as described in Appendix C, "List of Major Startup Tests and Checks", of our August 13, 1979, letter. All testing in the Startup Phase is controlled by the Startup Matrix.
Some deviations from the original Appendix Care anticipated and are discussed in the following sections.
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VIRGINIA ELECTRIC AND POWER COMPANY TO Mr. Harold R. Denton, Director 1.
Appendix C, II-Reactor Coolant System, item #1, Vibration and Ampli-tude This test, whose objective is to monitor the main coolant pumps with vibration sensors, will be performed through a Special Test.
How-ever, it is not the intent of our program to instrument the main cooling piping to monitor vibrations.
This will be done on a "visual basis" during the running of the main coolant pumps.
Additional investigations will be made if any extraordinary conditions are noticed during the visual examinations.
- 2.
Appendix C, II-Reactor Coolant System, item #3, Integrated Hot Func-tional Tests This section remains essentially unchanged except for the additions of those items discussed in the Preoperational Test Phase.
- 3.
Appendix C, V-Power Conversion System, item #2, Components and In-dividual System, Section b.
Emergency Feedwater (Auxiliary) System The original plan to perform water hammer testing of the auxiliary feedwater piping while starting and stopping the auxiliary feedwater pumps has been deleted from the test program.
This testing was deemed unnecessary at this time as actual testing had been accom-plished several years ago after the feedwater expansion loops were installed and no alterations have been made to the lines since then.
The new steam generators have the same nozzle design, so all previous data would still apply.
Startup Matrix The Startup Matrix is designed to control the testing evolution through the remainder of the Startup Program for Surry Unit No. 2.
It is structured on a plateau basis.
All items identified on a lower plateau must be completed prior to advancing to the next plateau.
This sequencing may only be deviated from with prior approval of the Superintendent of Operations or his designee.
The Station Nuclear Safety and Operating Committee will review all deviations in accordance with the Nuclear Power Station Quality Assurance Manual.
The specific plateaus chosen are as follows:
- 1.
Phase I - prior to going above 140°F (Refueling Shutdown)
- 2.
Phase II - prior to going above 200°F (Cold Shutdown)
- 3.
Phase III - prior to Containment Integrity
- 4.
Phase IV - prior to going above 350°F/450 psig
- 5.
Phase V - prior to Criticality
- 6.
Phase VI - prior to going above 5% Power
- 7.
Phase VII - prior to going to commercial operation The detailed tests within the phases will. be available at the Surry Power Station for review.
The Startup Matrix is a worl~ing document and may be revised as necessary to incorporate additional test requirements. that may arise through the balance of the startup effort.
Additions or changes require prior approval of the Superintendent of Operations or his designee, as stated earlier.
e VIRGINIA ELECTRIC AND POWER COMPANY TO Mr. Harold R. Denton, Director Summary This letter outlines the program for the balance of the Startup effort in bringing Surry Unit No. 2 back to power.
The additional administrative and procedural controls provide the required assurance that the unit may return to power in a safe manner.
JLW/FHT/ smv: SAS cc:
Mr. James P. O'Reilly, Director Office of Inspection and Enforcement Region II Atlanta, Georgia 30303 Very truly yours, g;e,()A£1~
B. R. ~c:-
Manager - Nuclear Operations and Maintenance