IR 05000412/1987026

Insp Rept 50-412/87-26 on 870406-10.No Violations Noted. Major Areas Inspected:Preoperational Test Program,Including Witnessing of Tests,Review of Test Repts,Status Review of Test Deficiencies & Activities in QA Interface

ML20214T661
Person / Time
Site:	Beaver Valley
Issue date:	06/01/1987
From:	Florek D, Vankessel H NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20214T649	List: IR 05000412/1987026 ML20214T647
References
50-412-87-26, NUDOCS 8706100367
Download: ML20214T661 (12)

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U.S. NUCLEAR REGULATORY COMMISSION

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REGION I

t Report No. 50-412/87-26 Docket N ! License No. CPPR-105 Category B i

1 Licensee: Duquesne Light Company i Post Office Box 4 j Shippingport, Pennsylvania 15077 i

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Facility Name: Beaver Valley Power Station, Unit 2

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! Inspection At: Shippingport, Pennsylvania Inspection Conducted: April 6-10, 1987 Inspectors:

H. f. Va Ke s'il

Reactor Engineer date '

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Approved by: s [  !

0. Florek," Chief date ' /

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Test Program Section, OB, DRS 1 ,

i Inspection Summary: Inspection on April 6-10, 1987 (Inspection Report Number 50-412/87-26)

! Areas Inspected: Routine Unannounced Inspection of the Preoperational Test j Program, including the witnessing of preoperational testi, the review of preoperational test reports, the status review of Test Deficiencies, the

! review of activities in the QA interface, and the review of unresolved items ,

l identified by the inspector in previous inspections. The status of the MSIV l replacement project and the schedule for its completion were also reviewed.

I j Inspection Results: No violations were identified Note: For acronyms not defined, refer to NUREG 0544, " Handbook of Acronyms #

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8706100367 870604 l PDR ADOCK 05000412 O PDR

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Details lt Persons Contacted

. Duquesne Light Company (DLC)

R. Bernier, Test Engineer T. Brown, Test Engineer R. C. Callaway, Test Supervisor, Phase 2

• D. L.' Claridge, Compliance Engineer

N. J. Daugherty, Director Systems Testing-D. Dygert, Test Engineer

• J. P. Godleski, Sr. Test Engineer i

• D. C. Hunkele, Director QA Operations

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• J. D. Johns, Supervisor QA Surveillance

*T. P. Noonan, Superintendent Operations & Maintenance i

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R. Oliveri, Test Engineer J. S. Patterson, Test Coordinator

! *L. M. Rabenau, Lead Compliance Engineer

! P. Slifkin, Test Supervisor 4 J. Steinke, Test Engineer

• G. R. Wargo, Assistant Director QC

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L. P. Williams, Director Startup j R. G. Williams, Software Development Supervisor i U.S. Nuclear Regulatory Commission

J. Beall, Sr. Resident Inspector, BVPS-2

D. Florek, Lead Reactor Engineer

L. Prividy, Resident Inspector, BVPS-2

i Denotes those present during the exit meeting held on April 10, 1987.

1 Licensee's Actions on Previous Inspection Findings i (Closed) Unresolved Item 86-22-03, " Administrative Controls for temporary j strainers in pump suction lines"

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Scope

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The adequacy of administrative controls concerning temporary strainers

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References

, TCN No. 2 of procedure P0-2.07.02, Boric Acid System", dated

6/18/86

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3 SWR 12647, dated 2-17-87 SWR 12648, dated 2-17-87 SWR 11233, dated 12-26-86 SWR 11234, dated 12-26-86 SWR 11235, dated 12-26-86 SWR 8950, dated 10-31-86 SWR 8951, dated 10-31-86 SWR 8952, dated 10-31-86 Startup Manual

Chapter 3.4.14, " Control of Temporary Electrical and Mechanical Bypasses and Defeating Devices"

Chapter 8.2.1, " Administrative Guidelines for Performing Tests" Discussion It was found that procedure P0 2.07.02 " Boric Acid System", did not contain a prerequisite step to remove the temporary strainers. The licensee has established that P0 2.07.02 originally contained a pre-requisite to remove the Boric Acid Transfer Pump Strainer's 2 CHS-STRT 103 and 104 baskets. Non intent Test Change TCN #2 (ref. 1)

for P0 2.07.02 deleted this prerequisite and allowed the startup strainers to remain in place for added cleanliness control TCN #2 also added steps to install pressure gauges and provided precautions for monitoring strainer pressure differential. These strainer baskets were tracked for removal on the " Jumper and Lifted Lead Log" and have since been removed on SWR 12647 and 12648. The other temporary strainers shown in Attachment B of Inspection Report 50-412/86-22, STRT 100-107, have also been removed in the same fashion, as follows:

Strainer N Startup Work Request N FWE - STRT - 100 SWR 11233 2 FWE - STRT - 101 SWR 11234 2 FWE - STRT - 102 SWR 11235 2 CHS - STRT - 105 SWR 8950 2 CHS - STRT - 106 SWR 8951 2 CHS - STRT - 107 SWR 8952 Findings

The inspector has no further questions on this unresolved ite (Closed) Unresolved Item 86-38-02, "Use of Butterfly Type Valves for flow control in Residual Heat Removal System (RHRS)"

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Scope The difficulties experienced with flow control above 2000 gpm during the Phase-1 Preoperational Test for the Residual Heat Removal System (RHRS),

procedure 2 TRHS-10-2.01, performed during inspection 86-38, led the inspector to question the adequacy of flow control with the existing butterfly type valves above 2000 gp References Memorandum from the Westinghouse Support Engineering Team (WSET),

BV-2-SET-074," Unresolved Item 86-38-02", dated March 30, 198 Discussion WSET reviewed the application (see ref.1 above) of butterfly valves for flow control and determined that the available system control accuracy of 5% is adequate to control the cooldown rate with some amount of operator action. There is ample time during the cooldown (administra-tive limit of 50 F per hour) to make flow rate adjustments. Westing-house has no knowledge of any RHR control problems attributable to the RHRS butterfly flow control valve Conclusion The 1.spector has no further questions on this Unresolved Ite . Preoperational Test Program 3.1 Properational Test Witnessing Scope Selected steps of the preoperational test procedures listed in Attachment A were witnesse Test witnessing included observations of the attributes listed in Section 3.2 of inspection report 50-412/86-2 Discussions Step VII L.9 of procedure P0-2.01 A.02 RPS and ESFAS Time Response Test, was witnessed. One relay failed to perform (99A2-81-VA-200). A replacement relay is on order. After replace-ment or repair of the relay, the pertinent test steps will be repeate Steps VII B 3,4, and 5 and VII B 7, 8, and 9 of procedure P0.-2.01A-04, Safeguard Test Cabinet Actuation Test, were witnessed on April 7 and 9 respectivel Step VII B.4.C.5 did not work properly. After review of the elementary diagram, it was concluded that subitems 5 and 6 could not work properly when the relays are tested one at a time because reset and start are on the same circuit.

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Test Deficiency No. I was written against this ite It will require a design change to the circuit to remedy this surveillance proble A Re' quest for Information (RI No. SVG-2613) was generated by the test

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engineer to initiate action by Stone and Webster (SWEC) to correct the situation. This RI points out that there will be future problems with surveillance testing because "both actuate and block signals

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originate from the same slave relay. After the fix a rerun for items 5 and 6 will be performed. The prerequisites IV P h and 1 for test steps VII B 7,8, and 9 presented a problem because there was no power to the green light (see elementary drawing 12241-E-11AL, sheet 2).

The test was performed without the alarm. Also SWS*A0V 118B and SWS*SOV 130B did not operate when relay K6098/K609XB was energize It was found that SWS*A0V118B was closed and SWS*SOV130B was open when "SI" was initiated due to lifting a lead at the SSPS output cabinet after the valve was initially opened. The valves were posi-tioned correctly and Run No. 2 was performed with satisfactory result Test Deficiency (TO) No. I was written against this proble TD #1 was closed after the satisfactory conclusion of run # The inspector will follow up on the new test deficiencies as part of

the overall review of test deficiencies of the POT program

) Emergency Diesel Generator (EDG) B (2-2) was run under Full Load conditions to satisfy the vendor's representative that the cylinders are adequately balanced. The inspector independently took tempera-

ture data (see Attachment D) on the cylinder exhausts after approxi-mately 40 minutes of operation under full load. (4200 kw) The l maximum temperature spread between the cylinders appears to be 130 F.

. Temperature element 2 however is suspect. Ignoring the reading for

! cylinder No. 2 the maximum spread narrows to 90 F. Later readings indicate a maximum spread of 105 F. This maximum spread at full load is considered to be adequate in terms of cylinder load balancin .2 Preoperational Test Result Evaluation Scope The Test Result Reports (TRR ) for the test procedures listed in Attachment B were reviewed to verify that adequate testing was accom-plished in order to satisfy regulatory guidance and licensee commit-

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ments and to ascertain that uniform criteria were being applied for evaluating completed preoperational tests to assure their technical ]

and administrative adequac .

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Discussion -

l The TRRs were reviewed for the attributes listed in Inspection Report 50-412/87-19. Each TRR was reviewed together with the file containing the completed original of the procedure and the correspondence asso-ciated with completed work and retesting for identified test

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deficiencie t It was noted again that many of the. test deficiencies (TDs) had been ( 3 processed satisfactorily prior to the completion of the test repor In the case of procedure 2.01A.10, 28, test deficiencies were pro-cessed to completion including retests. No test deficiencies remain

! to be tracked for this procedure. The work orders and retest infor-

mation were all included in the procedure fil For procedures- ,

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P0-2.12 B.01.and PO 2.47.05, TD's were also found to be satisfactor-ily processe '

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Findings No Non-compliances were identified by the inspecto .3 Test Deficiencies Scope

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A number of test deficiencies (TDs) were identified in the TRRs dis-

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cussed 9nder paragraph 3.2 above. These TDs will be tracked by the NRC to completion. They will also be evaluated for safety signifi-

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cance and the timing of completion relative to the major milestones

! of the start up program, i.e. Fuel Load, Post Core HFT, Initial Crit-t icality, Low Power Testing Power escalatio I

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Discussion The TDs requiring retest, as identified in the TRRs discussed under paragraph 3.2_above, have been listed in Attachment C. It is planned to assign an Unresolved Item Number to these TDs as soon as the NRCs ,

test result evaluation effort approaches 80%. A summary listing of TDs (with retests) will then be produced together with the evaluation of the safety significance of the listed TD's.

Findings e

No non-compliances were identified by the inspecto ,-

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4. Independent Inspection Effort 4.1 Independent calculation of Leak Rate for Fuel Transfer Tube Flang Scope Based on test data obtained during the performance of preoperational test PO 2.47.05, the inspector independently calculated the leak rate for the Fuel Transfer Tube Flang Reference Test Procedure P0-2.47.05, Containment Type B Leak Rate Test for Fuel Transfer Tube Flange", Rev. O, approved by JTG on November 29, 1984; Data sheet 1 for run No. I and No. 2, signed on January 29, 198 Discussion There were two runs to determine the leakage rate on the flange. On the basis of the test data collected, this leak rate has to be calculated in SCFD (Standard Cubic Feet per Day) using a formula based on well known gas laws. Tne answers developed by the inspector agreed very closely with the answers shown in the repor Conclusion No errors were found in the leak rate as calculated for runs 1 and 2 in the data sheets of reference 1 abov .2. Status MSIV Replacement MSIV replacement work is proceeding on schedule. Weld preparations for all 3 valves have been completed. The spool pieces to be used with the new Atwood Morril valves are being fabricated. The new valves are being re-conditioned in the vendor's shop. All three valves are scheduled for completion of installation by June 21, 198 The Phase 2 testing of these valves under procedure P0 2.21A.03 will be done after Fuel Loadin . QA/QC Interface Scope The participation of the Duquesne Light QA Surveillance Group in the pre- .

operational test program was evaluated by the inspector. A response by I startup management to a Surveillance Deficiency Report (SDR) was reviewe l l

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.h Surveillance checklist, SurvefilancejNd._ ;ICG-01-87 for 2 MSP-6.42-I,

, 'Rev,1, " Pressurized Level Loop 2 RCS-L4,60 Protection Channel II Cali-

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bration", prepared on February 24, .10L71,

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• Surveill'ance Deficiency Report for Deficieacy No. 1 of Surveillance

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No. ICG-01-87, dated February 26, 198 '

s Responsh' Letter from SUG on QA Surveillance No. ICG-01-87 (re abcve), dated March 27, BVPS:RJS:12241:390 . Ref.2 signed off as closed in response to re ., closed date April 3, 198 ,

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10A Surveillance No. ICG-01-87 (ref. 1) was-reviewed together with the Sur-veillance Deficiency Report for test deficiency No.1 (ref 2) the response e letter from SUG (ref. 3) and1the, response by QA (ref. 4).

The deficiency observed conceraed the absence of double signatures to-j , ," ' confirm system restoration steps and lack of detailed information to perform step VII.R.4. SUG was able to convince QA that the double sig-natures are nct needed and that training by Westinghouse should take care of the second item. QA agreed (ref. 4)

Findings The inspector agrees with the responses of SVG and QA and has.no question . Exit Interview

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At the conclusion of the site inspection on April 10, 1987, an exit-inter-view was conducted with the licensee's senior site representatives (denot-ed in Section 1). The findings vere identified and previous inspection items were discusse At no time during this inspection was written material provided to th licensee by the inspector. Based on the NRC Region I review of this re-port and discussions held with licensee representatives during this in-spection, it was determined that this report does not contain information subject to 10 CFR 2.790 restrictions.

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Attachment A to 412/87-26 Test Witnessing Procedure Revision Approval Number Title Number Date P0-2.01A.02 RPS and ESFAS Time 0 11-24-86 Response Test P0-2.01A.04 Safeguards, Test Cabinet 0 01-26-87 Actuation Test P0-2.368.02 Emergency Diesel Generator 0 11-18-86 Full Load Test

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Attachment B to 412/87-26; Beaver Valley -2 Test Result Evaluation Approval Procedure Revision Date Number Title Number IRR by JTG P0-2.11A.02 Safety Injection Check 0 12-02-86 Valve Test PO-2.01A.10 Reactor Protection System and 0 07-32-86 Engineered Safety Feature Actu-ation System logic Test P0-2.12B.01 Containment Leakage Monitoring 0 12-17-85 System Test P0-2.06.13 Reactor Vessel Head Vent System 0 04-03-87 Test P0-2.47.05 Containment Type B Leak Rate 0 03-09-87 Test for Fuel Transfer Tube Flange

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Attachment C to 412/87-26; Beaver Valley-2 Open Test Deficiencies Procedure Number TD N Remarks PO-2.11A.02 20 Retest Log No. 11A.001 (after Core Load)

4,7,8-17, Retest Log No. 11A.002 19,21,22 (after Core Load)

-P0-2.06.13 E&DCR Retest Log No. 6-002 00022S09 .

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Attachment D to 412/86-26 EDG-B Cylinder Exhaust Temperatures at Full Load Cylinder N Temp. F 1 820 2 740 3 840 4 830 5 870

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