IR 05000443/1986019

Insp Rept 50-443/86-19 on 860324-28 & 0428-0502.No Violation Noted.Major Areas Inspected:Preoperational Test Program, Including Test Witnessing of Preoperational Tests & Evaluation of Test Results of Completed Tests

ML20211J982
Person / Time
Site:	Seabrook
Issue date:	06/20/1986
From:	Eselgroth P, Nicholas H, Vankessel H NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20211J954	List: IR 05000443/1986019 ML20211J949
References
50-443-86-19, NUDOCS 8606270120
Download: ML20211J982 (15)

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U.S. NUCLEAR REGULATORY COMMISSION

REGION I

Report N /86-19 Docket N License N CPPR-135 Category B Licensee: Public Service of New Hampshire

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P.O. Box 330 Manchester, New Hampshire 03105 -

Facility Name: Seabrook Static q Jnit No. 1 Inspection At: Seabrook, New Ho.upshire Inspection Conducted: Sarcb 24 - RS, and April 28 - May 2, 1986 Inspectors. h/ di-24- N E van'Kess I eactor ngineer date ichola

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[26-date Tb Approved by: [ 28- N P3C Eselgrot , hief, Test Programs date Section, , DRS Inspection Summary: Inspection on March 24 - 28, 1986 and April 28 - May 2, 1986 (Inspection No. 50-443/86-19)

Areas Inspected: Routine unannounced inspection of the preoperational test program including the test witnessing of preoperational tests, the evaluation of the test results of completed tests, independent verification of test measurements, review of activities in QA/QC interface for POT program, and the review of unresolved items identified by the inspector in previous inspection Results: No violations were identified

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DETAILS 1.0 Persons Contacted Public Service of New Hampshire

• J.0. Azzopardi, QA Engineer (YAEC)

• R.W. Gregory, Licensing Engineer (WE&C)

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• R.E. Guillette, Assistant Constr. QA Manager (NHY) Gwinn, Startup Engineer (NHY)

• G. A. Kann, Test Group Manager (NHY)

• Kii ' P on, Compliance Manager (NHY)

• D.C. Lamoert, Field QC Manager (UE&C) Mackenseu, Tech. Support Supervisor (NPSH)

W.T. Middleton, QA Engineer (YAEC)

B.E. O'Connor, SQC Engineer (UE&C)

D.W. Perkins, QA Engineer (YAEC)

V.W. Sanchez, Engineer (YAEC)

J.G. Tefft, Project Engineer-STD (NHY)

• D.F. Turner, QA Engineer (YAEC)

• B.E. Wolfe, SQC Engineer (YAEC)

• Denotes those present at exit interview on May 2, 198 .0 Licensee Actione. on Previous Inspection Finding's (Closed) Unresolved Item 443/85-02-01, " Lack of Cross referencing of procedures GT-M-03 with 1 PT-27.1 and of GT-I-III with 1AT-31".

Scope:

The licensee was to revise IPT-27.1 " Fuel Storage Building Ventilation System" and 1AT-31 seismic monitoring to include GT-M-03 and G-I-III respectively to assure full coverage of system requirement Discussion:

The ventilation flow balancing to be conducted per FSAR Chapter 14, Table

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14.2-3, is done under procedure GT-M-03. The licensee has added GT-M-03, the HVAC test and balance procedure, to IPT-27.1, rev. 1 under acceptance i

criteria (8.2).

In the case of IAT-31, procedure G-I-III, for the installation and in-spection of the three trip type monitors, was added to the Pre-requisites (3) of 1AT-31 (rev.1) for completion prior to the tes This item is close '

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(0 pen) Unresolved Item 85-30-01, " Operational problems with MSIV Bypass Valves, Steam Dump Valves, and EFW System".

Scope:

The licensee is to resolve problems with: Capability of the Steam Dump valves to operate from fully closed to fully open within 3 seconds. Non-Conformance Reports NCR 82/924A and 973A were issued by the licensee to address this proble . Capability of the MSIV Bypass Valves to open against normal pressure differential and to close under normal conditions. Non-Conformance Report NCR 82/937F was issued to address this proble a Water hammer during initial cold start, of the EFW system which caused damage to pipe supports. RFI 99/109088 was issued to request engineering evaluations and proposals to remedy the water hammer problem in the futur b The air operated steam supply valves to EFW pump turbine (MS-V127 and V128) failing to open on a loss of power with a delta P of 1080 ps NCR 82/967A was issued to address this proble c The minimum flow recirculation lines limiting long term recirculation to 20 minutes with both EFW pumps runnin The deficiencies were j documented in NCR 82/99 '

3d The ESF pumps not meeting the performance requirements of the FSAR (section 15.2.8.2, page 15.2-20). NCR 82-994A was issued for engin-eering evaluation. A contributing factor to the above problem was the failure of both EFW pumps to meet the manufacturer's pump curve NCR 82/993A was issued to address this problem (IIL-FW-01222).

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Discussion Re 2: The disposition of the MSIV - Bypass valves in NCR 82/937F (sheets)

consists of increasing the gear ratio from 43.6/1 to 109/1 and other changes to the spring pack and torque switch to increase available output torque above 200 ft lb. As a result of these changes, the closing time of the valve will increase to approx. 25 to 30 seconds. There are however, no FSAR requirements for valve stroking time. This valve modification work will be accomplished by Limitorque at Rockwell International's facilitie The same motors will be used. This sub item will remain open until in-stallation and retesting of the modified valves have been accomplishe .

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Re 3a: The water hammer issue was reviewed by the inspector in Inspection Report 50-443/86-13. This item will be kept open until the retest of the modified steam supply and cor.densate drain system has been completed successfull Re 3b: Steam supply valves MS-V-127 and V128 will not operate under design conditions. These are Velan, air operated, valves. After valve testing in the presence of a Velan service engineer, it was established that the valve will function with air pressure above 70 psig. Velan's recommendation is to increase operating air pressure to 70-75 psig. Then the recommendation was validated by functional test. This subitem can be close Re 3c: The system modifications to solve the problem of the recirculation lines of the EFW pumps is described in ECA-08802575C. Basically, the existing full flow ANSI B31.1 test recirculation piping of crisscross configuration will be replaced by ASME III, class 3 piping which will go directly to the Condensate Storage Tank. The use of the non-ASME recir-culation line during the full flow 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> endurance run, with both EFW pumps running, already has verified that over heating will not occu This sub item will remain open until installation and retesting of the modified piping have been accomplishe Re 3d: The FSAR requirements were found to be erroneous. FSAR 6.8.2 will be revised to read: "The open position of the flow control valves will be set to insure that the minimum required flows of 470 gpm and 650 gpm for one pump operation to 3 and 4 steam generators respectively for system limiting conditions". FSAR table 15.0-8 will also be revised to clarify system capacity in a similar manner. The system is being redesigned to assure that the new FSAR requirements are met. This sub item will remain open until installation and retesting of the modified system have been accomplished. With regard to the problem of the pumps in meeting the pump test curve, it was established that the subject pumps meet the criteria of specification 238-10 and are therefore acceptabl .0 Preoperational Test (POT) Program 3.1 Test Procedure Review Scope The test procedures listed in Attachment A were reviewed for admini-strative and, selectively, for technical adequacy and to verify that test planning satisfies regulatory guidance and licensee commitment '

Discussion The procedures were examined for:

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Management review and approval

Procedure format

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• Clarity of stated objectives i

• Prerequisites

Environmental conditions

• Acceptance criteria and their sources

References

Initial conditions

• Attainment of test objectives

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• Test performance documentation and verification

• Degree of detail for test instructions

Restoration of system to normal after testing

Identification of test personnel

Evaluation of test data

Independent verification of critical steps or parameters

Quality control and assurance involvement Findings No noncompliances were identified by the inspector within the scope of this inspectio .2 Test Witnessing Scope The Loss of Offsite Power Test With Engineered Safeguard Features (ESF)

Actuation, IPT-39.2, was witnessed by the inspectors. The objectives-of the Loss of Offsite Power With ESF Actuation test are as- follows:

(1) To verify the independence of the redundant onsite power sources during a loss of offsite power (LOP)-coincident with an engineer-ed safeguard features .(ESF) actuation. Two tests will be run independently with one train de-energized while the other train

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(2) To verify that during diesel generator starts from an auto-start signal, permanently connected loads are energized, auto-con-nected emergency loads are energized at the direction of the emergency power sequencer and all loads are operated for at least five minutes. After fully loading the diesel generator, the bus voltage and frequency are maintained at their prescribed values for the duration of the even (3) To verify that during initial loading, the voltage and frequency of the emergency busses r7 cover to no less than 80% and 95% of their nominal values, respectively, within six cycle (4) To verify that during sequential loading of the auto-connected loads, the emergency bus voltages and frequencies decrease to no less than 80% and 95% of their nominal values, respectively, and that bus voltage and frequency are restored to within 10%

and 2% of their nominal values, respectively, in less that 60%

of each load sequence time interva (5) To verify the DC load profiles for each trai (6) To verify proper equipment operation such as: LOP, Emergency Power Standby (EPS) sequencing complete, followed by an ESF signal, as well as; LOP, EPS sequencing interrupted by an ESF signa (7) To verify proper equipment response to an ESF signal with a delayed LO (8) To verify proper equipment response to an ESF signal with a coincident LOP and (cooling) Tower Actuation (TA) signa (9) To verify proper equipment response to an ESF signal while the diesels are operating in parallel with offsite powe (10) To verify ESF response time for safety-related pump (11) To verify primary component cooling water flow after automatic realignment of primary component cooling water valves caused by temperature and pressure signal (12) Record DG voltage and frequency response while tripping a 1500 HP load with the diesel carrying a majority of accident loads, s

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Discussion The inspector reviewed the latest approved copy of procedure PT-3 Revision 1, approved March 24, 1986 titled, " Loss Of Offsite Power With Engineered Safeguard Features Actuation". All exceptions and changes were reviewed, as well as objectives, references, prerequi-sites, precautions, initial conditions and acceptance criteri The following seven tests of the Loss Of Offsite Power With Engineered Safeguard Features Actuation procedure were witnessed by NRC inspector (1) Train A Loss of Offsite Power With Safety Injection (SI) Signal-Train B De-energized (2) Train B Loss of Offsite Power With SI Signal-Train A De-energized (3) Loss of Offsite Power with ESF After Emergency Power Sequencing Completed (4) Loss of Offsite Power with ESF During Emergency Power Sequencing (5) ESF Actuatio, with Spray Actuation (simulated) followed oy Delayed Loss of Power and Tower Actuation (Cooling Tower)

l (6) Loss of Power With Coincident ESF Actuation and Tower Actuation and Spray Actuation (simulated)

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(7) Parallel Operation of Diesels With Offsite Power With I Coincident ESF Actuation.

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Findings Electrical train independence between emergency buses was observed during the performance of the tes Emergency bus loads shed and '

automatically started in response to a loss of power and all loads operated for at least five minutes. During loss of power sequencing, an ESF signal restarted the emergency bus load sequence. Emergency loads auto-started in response to safety injection and containment spray actuation signals. Proper equipment response was observed upon a tower actuation while operating on both diesels. Diesel generators operated without service water flow through the diesel Jacket water heat exchangers during a delayed TA after a LOP sequence, and during a simultaneous LOP and TA actuation, without temneratures exceeding 180 F. During auto-load sequencing and a short time period af ter sequencing, the total connected load was no greater than 6697K _

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Proper equipment response was verified during coincident ESF signal, loss of power and tower actuation TA signal. The startup feedwater '

pump was operated after all available accident loads were energized without causing steady state voltage and frequency to drop below 3740 Volts and 58.8 Hertz. The diesel generator voltages and frequencies did not decrease below 80% (3328 Volts) and 95% (57 Hz) of nominal values, respectively and voltage and frequency were restored to at least 90% and 98% of their nominal value within 60% of each load se-quence time interval, and during diesel generator operation in paral-lel with offsite power, proper equipment response to an ESF signal runs observe No discrepancies or noncompliances were noted by the inspecto .3 Test Result Evaluation Scope

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The test procedures listed in Attachment B were reviewed to verify that adequate testing was accomplished in order to satisfy regulatory guidance and licensee commitments and to ascertain whether uniform criteria were being applied f or evaluating completed preoperational

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tests in order to assure their technical and administrative adequac Discussion l The test results were reviewed for:

• Test changes *

• Test exceptions

Test deficiencies

• Acceptance criteria

Performance verification

I a Recording of conduct of test

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• QC inspection records

• System restoration to normal

Independent verification of critical steps or parameters

Identification of test personnel

Verification that the test results have been approved i

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It was noted that two of the procedures showed omissions of sign-offs in the completed and approved test results, ie. procedures PT-3 and PT(I)-37.2. These omissions were discussed with startup manaae-ment. A commitment was made to look into the inspector's question and provide a response during the next inspection. The inspector will follow up on this item in a future inspectio Findings The omission sign offs on PT-34.1 and PT(J)-37.2 will be Unresolved Item 50-443/86-19-02. Apart from these omissions, no discrepancies or unacceptable conditions were noted in the review of,these procedures except for the following test exception Procedure Title Exceotion No.* Open Items j PT-1 RW5T and SAT 01 1 Drawdown test PT-2 Backup Hydrogen 01 1 Purge PT(I)- Piping Vibration 01,02 2 Testing

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PT-31 125 VDC 01,02,03,04,05 2 Distribution i

System PT-26 Containment Air 01 1

• Underlined items are open items l PTI-3 Reactor Contain- 01,02 2 ment, type B & C PT-3 Fuel Handling 01,01 0 Equipment ~

PT-3 Emergency Diesel 01,02,03, 3 Generators 04,05,06,

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07,08,09, 10,11 AT-25 Turbine Building 01,02 1 Ventilation AT-5 Chlorination 01,02 1 These open items, collectively, are designated unresolved Item ,

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4.0 New Fuel Receipt Inspection and Storage References References are documented in Inspection Report 50-443/86-I Scope The objective of this inspection was to ascertain whether nuclear fuel received at the construction site is properly accepted and safeguarded, and whether it is stored in accordance with the NRC license requirement This was accomplished by direct observation of activities and review of documentation at various times prior to the issuance of the NRC materials license and the arrival of the first shipment of nuclear fuel, and by wit-nessing of the first shipment of fuel, from its arrival on site, to its ,

final storage place in the new fuel storage are Discussion The inspector witnessed inspection and storage of 4 fuel assemblies from removal from the shipping casks to storage in the new fuel storage are The activities included radiation surveys of the outer metal casks; onen-ing of the casks; initial survey of the two fuel assemblies in each cask; the removal and inspection of each fuel assembly; and the final storage of each fuel assembly in the new fuel storage area. The inspector observed the use of fuel handling cranes, new fuel handling tools, personnel involv-ed, procedures being used, HP monitors and QC participation. The inspector also witnessed the movement of ten fuel assemblies from the new fuel stor-age area to the spent fuel pool. The inspector also reviewed documentation and maae o

&bservations, on a sampling basis, during this evaluation, in the areas of Administration, Physical Security, Health Phy-

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sics and Radiation Control, Reactor Engineering, Quality Assurance and Quality Contro Findings The inspector verified that receipt, inspection and storage, including documentation, was cccomplished in accordance with NRC license require-ments. The inspector also verified that all license requirements had been implemented for new fuel receipt inspection and storage; security controls'

were exercised; health physics and radiation protection controls were im-plemented in the areas of swipes, surveys, air monitoring, and personnel protection and dosimetry, control of the environment of the fuel storage area; verification of documentation; inspection of shipping casks; and, qualification'of personnel involved in management and implementation of receipt, inspection, and storage of nuclear fuel. The inspectors witness-ed the evolutions and verified documentation and proper use of procedures for fuel movement within the fuel building and fuel storage location . ,,. , , - - - - - - - - * - - ~' ~~

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t No items of noncompliance were identified and no discrepancies were noted during these inspections. The inspector will continue to observe and in-spect this evolution of new fuel receipt, inspection, handling and storage on subsequent inspections until all fuel is on site. - The inspector had no further question at this tim .0 -Startup Test Program i

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The inspector reviewed the status of the program in preparation for imple-mentation of the startup test inspection program which will encompass ini-tial fuel loading, initial criticality, low power testing, and power ascen-

sion testin Discussion

The inspector obtained the startup test program manual, the startup test administration procedure, and the startup test index of procedures, of 1 which 49 of 57 startup test procedures have been received for review. The startup test program will be conducted in three phases:

a) Phase 4, Initial Fuel Loading b) Phase 5, Initial Criticality and Low Power Testing c) Phase 6, Power Ascension Testing The inspector prepared a matrix of licensees startup test procedures as a cross-reference with NRC inspection requirements, .and verified that all

NRC required tests are included in the licensees procedures and the startup i

test program. A sequential testing chart has been prepared showing the sequence of testing from fuel loading to the warranty run including the NRC mandatory tests to be witnesse Findings Based on discussions with licensee representatives and reviews of the

{ startup test program administrative documents, the startup test program appears to be well defined and has adequate administrative controls for

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the required testin The inspector had no further concerns in this are .

6.0 Independent Inspection Effort Scope Calculations were made to check the available Net Positive Section Head (NPSH) for Containment Building Spray Pump CBS-P-9A and Residual Heat Re-l moval Pump RH-P-9A as used in preoperational test procedure IPT-11, Rev. 2.

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Discussion i NPSH available is equal to the absolute pressure at the pump inlet plus

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velocity head minus vapor pressure (at pumping temperature) plus gauges i corrected to the elevation of the pump centerline. Calculations showed that the NPSH available for both pumps is in excess of the NPSH required as provided by the manufacturer of the pumps.on the test curves. This j indicator that the pumps will not be subject to cavitation which could

damage the pump impeller (pitting).

Findings No errors were found in the pertinent test results.

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7.0 QA/QC Interface 1

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Scope The participation of the YAEC Field QA Group in the test witnessing of the LOP Test (PT-39.2), the Containment Structural Integrity Test (PT(I)-36),

the Containment Integrated Leak Rate Test (PT(I)-37.1), and the Piping Vibration Test (PT-3.4), was evaluated by the inspecto I'

Discussion In continuation of the assessment of QA/QC involvement with the preoper-

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ational test program, the inspector reviewed the surveillance reports as listed in Attachment C. All of these listed surveillances are samples of test witnessing of the tests indicated in the scope of this inspectio The review of these surveillances indicates adequate coverage of these tests.

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Findings i

No noncompliances were observed within the scope of this-inspectio .0 Exit Interview

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At the conclusion of the site inspection , an exit interview was conducted -

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with the licensee's senior site representatives (denoted in Section 1). '-

The findings were identified and previous inspection items were discussed.

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At no time during this inspection was written materirl provided to the li-censee 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

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10 CFR 2.790 restriction .

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ATTACHMENT A Test Procedure Review Item No. Proc. No. Title Revision No. Appr. Data 1 AT-1 Halon Systems Testing 0 3/21/86

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2 PT-15.11 Service Water Cooling 0 2/26/86 Tower Portable Makeup Pumps 3 PT-15.12 Service Water System 1 2/28/86 Pump house HVAC 4 AT-2 Extraction Steam and 0 3/26/86 Heater Drain Systems 5 PT-3 Fuel Handling and 0 4/2/86 Transfer Equipment 6 AT-1 Post-Accident Sampling 0 3/31/86 System 7 AT-30 Radiation Monitoring 0 4/2/86 System Control Interface Test 8 PT-2 Control Room Air 1 3/21/86 Conditioning 9 AT-67 ECCS and RMW Storage Tank 0 4/11/86 Heating Systems 10 AT-5 Miscellaneous Sump Pumps 0 4/11/86 and Unit Heaters 11 PT-1 Service Water Pumps and 0 4/23/86 Tower Actuation 12 PT-1 Service Water Cooling Tower 1 4/23/86 13 PT-3 Emergency Diesel Generator 0 4/30/86 Reliability Tests 14 PT-1 RWST and SAT Drawdown Test 0 3/26/86 m

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ATTACHMENT B Test Results Evaluation Review i

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Item No. Proc. N Title Revision N Appr. Data i

1 PT- Piping Vibration 0 10/16/85 Test results approved 4/25/86 2 PT-11 Containment Recir /6/84 Sump Operation Test results approved 4/25/86 3 PT-1 RWST and SAT Draindown Test 0 3/26/86 Test results approved 4/16/86 4 PT-15.10 SW Pump Trip-Start 1 3/7/86 Test results approved 3/12/86 5 PT-15.12 SW Pump House HVAC 1 2/28/86 Test results approved 3/5/86 '

I 6 PT-2 Containment Enclosure 0 9/18/85 Test results approved 3/21/86 7 PT-2 CGC Recombiners 0 10/31/84 Test results approved 4/9/86 8 PT-2 CGC Backup Purge 0- 2/5/86 Test results approved ~4/11/86 9 PT-26 Containment Air Recir I 1/8/86 Test results approved 4/16/86 10 PT-31 12J VDC Distribution 1 11/21/85 Test results approved 4/25/86 11 PT-3 Emergency Diesel 1 1/10/86 Test results approved 4/18/86 12 PT-3 New Fuel Handling 1 1/10/86 Test results approved 4/18/86 13 PT-3 Containment Type B & C Test 1 1/10/86 Test results approved 4/18/86 14 AT-25 Turbine Building Ventilation 0 10/10/84 Test results approved 8/30/85

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Item N Proc. No. Title Revision No. Appr. Data 15 AT-52 Circ. Water Pump House 0 4/19/84 Heating and Ventilation Test Test results approved 4/19/84 16 AT-53 MS and FW Pipe Chase Ven I 10/9/85 Test Results approved 3/20/86 17 AT-5 Chlorination Test 0 8/8/85 Results approved 2/18/86 '

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ATTACHMENT C to 50-443/86-19 Review of Survellance Reports (SR) Issued By YAEC FQAG SR N Test Proc. Observed TP Title Rpt Date SR Y-1209 PT-3 Cont-Type BZ Tests 3-19-86 PT(I)-37.1, Re Cont. ILRT 3-19-86 Y-1218 PT(I)-36, Re Containment SIT 3-16-86 Y-1220 PT(I)-36, Re Containment SIT 3-17-86 Y-1236 PT- Piping Vibration 3-19-86 Y-1241 PT(I)-36, Re Containment SIT 3-20-86 Y-1249 PT(I)-36, Re Containment SIT 3-20-86 Y-1250 PT(I)-36, Re Containment SIT 3-20-86 Y-1251 PT(I)-30, Re Containment SIT 3-20-86 Y-1285 PT(I)-36, Re Containment SIT 3-21-86 Y-1303 PT(I)-36, Re Containment SIT 3-15-86 Y-1311 PT(I)-39.2(Train A) LOP Test W/ESF 3-25-86 Actuation Y-1312 PT(I)-39.2(Train B) LOP Test W/ESF 3-26-86 Actuation

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