IR 05000412/1986032

Safety Insp Rept 50-412/86-32 on 861020-24.Deviation Noted: Addl Correspondence Submitted for Preoperational Test Inadequate to Determine Net Positive Suction Head for Recirculation Spray Pump

ML20214U287
Person / Time
Site:	Beaver Valley
Issue date:	11/19/1986
From:	Florek D, Van Kessel H NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20214U068	List: IR 05000412/1986032 ML20214U065 ML20214U102
References
50-412-86-32, NUDOCS 8612090212
Download: ML20214U287 (8)

Text

{{#Wiki_filter:, . .- U.S. NUCLEAR REGULATORY COMMISSION

REGION I

Report N /86-32 Docket N License N CPPR-105 Priority - Category B Licensee: Duquesne Light Comoany Post Office Box 4 I Shippingport, Pennsylvania 15077 Facility Name: Beaver Valley Power Station, Unit No. 2 Inspection At: Shippingport, Pennsylvania Inspection Conducted: _ October 20-24, 1986

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Inspector: . lO [[ H. F." van ~ Ke,ssel, Rea tor Engineer date/ ' Approved by: .d Yf Y

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D. Florek, Chief, Test Program Section, date /~'/ 08, DRS Inspection Summary: Inspection on October 20-24, 1986 (Inspection No. 50-412/86-32) Areas Inspected: Routine unannounced inspection of the preoperational test program, including the review of Joint Test Group (JTG) approved procedures for ; preoperational test, the witnessing of preoperational tests, the review of ) activities in the QA interface, and the review of unresolved items identified by the inspector in previous inspections. The status of the preparations of the turbine, and its auxiliaries, of the turbine driven auxiliary feedwater pump for the phase-1 test (uncoupled run of turbine) was reviewed and the tur-bine was inspected in situ. The status of phase-1 tests for the Main Steam isolation valves was also reviewe Results: One deviation was identified for not determining NPSH available for the recirculation system spray pump (see Section 2).

NOTE: For acronyms not defined, refer to NUREG-0544, " Handbook of Acronyms and Initialisms."

~ C612070212 861128 2 ADOCK 0500

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~ Persons Contacted Duquesne Light Company (DLC)

R. C.- Callaway, Test Supervisor, Phase 2 C. Custer, Maintenance Engineer, Operations M. Covey, System Engineer

*A. W. Crevasse, Deputy QA Manager
*N. J. Daugherty, Director, Systems Testing
*J. P. Godleski, Senior Test Engineer
*D. C. Hunkele, Director, QA Operations
*J. D. Johns, Supervisor, QA Surveillance J. R. Kasunick, Director, Maintenance and Materials W. A. Kraycar, Test Engineer, NSSS J. Metzger, Test Engineer, NSSS T. Pietrangelo, Senior Test Engineer, BOP M. Robinson, Test Engineer
*C. K. Schulte, PRC Chairman
*R. J. Swiderski, Startup llanage *S. P. Verma, Assistant.Cirector, Phase-1 Testing
*R. Wa11auer, Lead Compliance Engineer
*L. P. Williams, Director, Phase-1 Testing R. G. Williams, Supervisor, System Testing Software
* Denotes those present at exit interview on October 24, 1986.

. ' U.S. Nuclear Regulatory Commission

*A. A. Asars, Resident Inspector
*J. C. Beall, Senior Resident Inspector
*H. Gregg, Lead Reactor Engineer
*A. J. Lodewyk, Reactor Engineer
*L. Tripp, Section Chief Licensee Actions on Previous Inspection Findings (Closed) Unresolved Item 412/86-25-01, " Adequacy of system restoration af ter test for PO 2.07.01 and PO 2.07.03." In a previous inspection, the restoration steps of procedure PO 2.07.03 were reviewed in detai In this inspection, the same type of review was applied to procedure PO 2.07.0 A restoration matrix, showing the installation and removal of temporary test devices by individual steps in the procedure, was prepared for test procedure P0 2.07.01. Again it was found that Section IV, Prerequisites, contained general instructions on the installation of jumpers and the lifting of leads to simulate SIS Block signals, Recirculation Mode Initiation signals, and Diesel Sequencing signals. In Section VII, how-ever, each of these simulations was identified separately and specific n

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instructions for the installation of jumpers and for the, lifting of leads were provided. The steps in Section VII to restore the system for each of the temporary system alterations introduced for the simulation mentioned above, were all found to be presen To further assure that system- restoration is accomplished without exceptions in all of the preoperational test procedures, the licensee agreed to review all of these procedures for this purpose exclusivel The inspector has no further questions on this item at this tim Unresolved item 412/86-25-01 is hereby close (Closed) Unresolved Item 412/86-27-01, " Missing NPSH determination in P0 2.13.01, " Recirculation Spray System."

Inspection Report 50-412/86-27 documented concerns that P0 2.13.01 did not determine available net positive suction head as committed in the FSA However, an unresolved item was identified for review of additional information. The inspector reviewed . correspondence on the NPSH test performed on the Recirculation Spray Pump in a scale model test tower at the Alden Research Laboratory. This review was made to determine if the scale model test obviated the need to determine NPSH available during the preoperational test. The additional correspondence did not supply infor-mation which obviates the need to determine available NPS FSAR paragraph 14.2.12.15.1, " Recirculation Spray System Pump and Controls Test," states under item 3 that "available net positive suction head will be measured." Since procedure P0 2.13.01 does not determine available NPSH, this is a deviation of your FSAR commitment. (412/86-32-02). This will close item 412/86-27-0 . Preoperational Test Program 3.1 Test Procedure Review Scope The preoperational test procedure P0 2.06.08, " Hot Functional Test," (HFT) has been reviewed for administrative and, selectively, for technical adequacy and to verify that test planning satisfies regulatory guidance and licensee commitment Discussion The test procedure was examined for the attributes listed in Inspection Report 50-412/86-1 The review of test objectives and test methods of the HFT procedure revealed some discrepancies when compared with the text of Section VII, Procedure, and with the commitments shown in Chapter 14 of the FSAR, as

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(1) FSAR paragraph 14.2.12.8.3, "RCP Seal Injection and Bearing Cooling Water Test," states under " Test Methods," item 5, that
 "During Hot Functional Testing, the flow rate of seal . water to and leak off from each RCP will be measured and adjusted, if required, using the system throttle valve" and under item 6:
 " Flow rate and temperature of the bearing cooling water and bearing temperature will be measured."-

The applicable procedure, P0 2.06.03, "RCP Seal Injection," however, is not used in the HFT procedure. A check against the

 " Hot Functional Milestone Schedule," dated August 8, 1986, confirms that it is not used during the HF (2) A number of preoperational tests (P0s) and System Operation Verifications (S0Vs) are shown in Section VII (Procedure) of the HFT procedure but are not shown under the test objectives or test methods (Section II). Two of the SOVs are scheduled to be done but do not appear anywhere in the HFT procedure, i.e., SOV 2.08A.01, Boron Recovery System, and SOV 2.35.02, Main Generator Electrical Tes It is recognized that, in view of the complexity of this inte-grated system test, adequate coverage of the above items may be achieved via incorporation in other test As such, the inspector will conduct additional review of the procedure and discussion with the license The inspector also noted that a number of tests are relegated to the startup test group (IST), in compliance with the FSAR statements in Chapter 14, but could be done, in part, during the HFT to obtain baseline data. An example would be the RCS Leak Rate tes While not specifically required in the FSAR, the inspector pointed out to the licensee that the HFT could be used as a tool to verify system performance as well as procedure adequacy prior to actual us Findings The clarification of the observations mentioned above will be pursued under Unresolved Item 412/86-32-01, 3.2 Test Witnessing Scope Selected steps of procedures P0 2.24B.01, " Motor Driven Auxiliary Feedwater Pumps and Controls," and P0 2.06.06, " Pressurizer Relief Tank (PRT) and Power Operated Relief Valves (PORVs)," were witnesse Test witnessing included observations of the attributes in Section 3.2 of Inspection Report 50-412/86-2 '

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Discussion Steps VII A.4.d(2) to VII A4.1 of procedure P0 2.24B.01 were witnessed. No unacceptable conditions developed. For the case of PO 2.06.06, a set point problem developed on 2RCS-MOV516, PRT Spray Valve, which kept the valve closed and kept the tank level constant at 72%. This test deficiency was recorded in the test log and the test deficiency form was reviewed after the test. The setting of the valve was adjusted and the instrument loop recalibrated. A retest was done the next day with acceptable result It was noted that the settings for MOV516 were not shown in the set point list PES 704 located in the control room. The inspector will check into this in a future inspection to determine if this is an isolated case or a more widespread proble Findings No violations were identifie . Independent Inspection Effort 4.1 Status of Turbine Driven Auxiliary Feedwater Pump Scope The preparation of the Terry Turbine for its phase-1 test, the uncoupled turbine run, was inspecte Discussion The Startup Work Requests (SWRs) pertaining to the preparations of the Terry Turbine for the nhase-1 test, the uncoupled turbine run, were reviewed by the inspecto The Woodward governor was returned to the vendor to be drilled for the magnetic pickup (N&D 12412). The governor had been calibrated prior to this operation. Bearing housing, gear pump, and reservoir of the lube oil system have been cleaned under SWR 7561. QC had checked on all of the activities and signed off on these action It was noted that two items had been signed off with dates in the future. It was established that the work had been done but that the dates were in erro The throttle and trip valve has been taken off to permit flushing of the lube oil system and steam blow of the steam piping. The present plan, however, calls for all parts, including the trip and throttle valve, to be reassembled on the turbine after the lube oil flush to keep all parts together. The trip and throttle valve will be removed again prior to the uncoupled turbine run (during HFT) to permit steam blowing of the steam supply lin y 1 T h :, .

   -6 SWR 5690 will clean the turbine's carbon packing rings, remove, set and reinstall the overspeed trip disc, and adjust the throttle and governor valve linkages. It will also cover the coupling of pump and turbine after the uncoupled turbine ru The work on the carbon rings and the overspeed trip disc ' ad r been completed a week ago but had not been recorded ye Inspection of the turbine in situ accurately reflected the equipment status indicated on the SWR Findings No unacceptable conditions were observed during this inspectio .2 Status of Phase-1 Tests for Main Steam Isolation Valves (MSIVs)

Scope The inspector obtained the latest information on the activities on the MSIV modifications planned by the vendor to correct several generic problems and the impact they have on the startup progra Discussion DLC management has decided to remove the valve balls and operators now and to blank the valve housings. This action will permit these valve parts to be modified at the vendor's shop at the earliest possible tim At the same time, it will not delay the HFT. The main turbine stop valves will be used as main steam isolation valves for this tes Conclusion The phase-1 and phase-2 tests for the MSIVs will be delayed without affecting the HFT schedul . QA/QC Interface Scope The participation of the Duquesne Light GA Surveillance Group in the preoperational test program was evaluated by the inspector. Samples of the surveillances performed on the most recently performed preoperational tests, including phase-1 and phase-2 tests, were obtained for this review and are shown in Attachment Discussion Of the surveillances reviewed, there were four Surveillance Deficiency Reports (SDRs).

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, The most significant deficiencies of the four SDRs are SDR #1 and #2 of POT 21-86. In SDR #1, jumpers were installed to make valves 2CHS*MOV 380A and B operate correctly and the test was continued. No test deficiencies were written and no corrective actions were noted in the test log as re' qui red by the Startup Manual (SUM), SUM 8.2.1, Section VI.B.8 on

" Notation and Disposition of Test Deficiencies."

For SDR #2, entries were made in the Test Log indicating the use of j jumpers which were not part of the approved procedure. These jumpers were not recorded on the Systems Testing Group Administrative Control Sheet or the - Control Room Jumper and Lifted Lead Log as required by SUM 8.2.1, Section VI.B.5 and SUM 3.4.14.

, Findings The QA discovered departures from the requirements of the Startup Manual were noted by the inspector. He will follow startup management's response , to these QA finding . Unresolved Items Unresolved items are matters about which more information is required in order to determine whether they are acceptable, an item of noncompliance, or a deviation. A new unresolved item in this report is identified in paragraph . Exit Interview f At the conclusion of the site inspection on October 24, 1986, an exit interview was conducted with the licensee's senior site representatives (denoted in Section 1). The findings were identified and previous inspection items were discusse At no time during this inspection was written material provided to the licensee by the inspector. Based on the NRC Region I review of this report and discussions held with licensee representatives during this inspection, it was determined that this report does not contain information subject to 10 CFR 2.790 restriction + - [ 't . ' 4 ATTACHMENT A TO 412/86-32 REVIEW 0F QA SURVEILLANCE REPORTS Date Sury. N Description Activity Test Proc. N Reviewed CPT-4-1-86 "A" _ Train Battery Rooms 2T-HVK-44 F-2.14 10/23/86' Exhaust Fan No SDRs* S0V-36-86 Chilled Water System SOV 2.29.01- 10/08/86 One SDR Section VI POT-20-86 Charging Pumps & Controls P0 2.07.01 10/13/86-Or.e SDR Section VI POT-21-86 Charging Pumps & Controls PO 2.07.01 10/08/86 Two SDRs

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Surveillance Deficiency Reports (SDRs)

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