IR 05000443/1986040

Insp Rept 50-443/86-40 on 860623-27.No Violations Noted. Major Areas Inspected:Preoperational Test Program,Including Preoperational Test Procedures,Evaluation of Test Results & Review of Actions on Unresolved Items

ML20203H151
Person / Time
Site:	Seabrook
Issue date:	07/25/1986
From:	Eselgroth P, Vankessel H NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20203H125	List: IR 05000443/1986040 ML20203H120
References
50-443-86-40, NUDOCS 8608040317
Download: ML20203H151 (12)

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U.S. NUCLEAR REGULATORY COMMISSION

REGION I

Report No. 50-443/86-40 Docket No. 50-443 License No. CPPR-135 Category B Licensee: Public Service of New Hampshire P.O. Box 330 Manchester, New Hampshire 03105 Facility Name: Seabrook Station, Unit N Inspection At: Seabrook, New Hampshire Inspection Conducted: June 23-27, 1986 Inspectors- 7-2 3~- M H'F. vanKe 1, Reactor Engineer date Approved by: 7-255%

P.W. Eselgr Chief, Test Programs date Section, DRS Inspection Summary: Inspection on June 23-27, 1986 Inspection No.50-443/86-40 Areas Inspected: Routine unannounced inspection of the Preoperational Test Program including the review of preoperational test procedures, the evaluation of test results, the review of test exceptions, the results of retests and the review of actions by the applicant on unresolved items identified by the in-spector in previous inspections.

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Inspector Results: No violations were identifie '

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

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8608040317 860725 PDR ADOCK 05000443 G PDR ( )

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DETAILS 1.0 Persons Contacted Public Service of New Hampshire J. O. Azzopardi, QA Engineer (YAEC)

S. H. Durphy, Startup Technical Support Supervisor-STD (NHY)

• R. W. Gregory, Licensing Engineer (UEBC)

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

G. Kotkowski, Startup Engineer (NHY)

• W. T. Middleton, QA Staff Engineer (YAEC)

• W. J. Mackensen, Startup Technical Support Supervisor (NHY)

• T. G. Pucko, Licensing Engineer (NHY)

• J. W. Singleton, Assistant QA Manager (YAEC)

• S. Stasek, Licensing Engineer (NHY)

A. Smith, Startup Engineer-STD (NHY)

L. Upson, Preoperational Test Schedule Supervisor (NHY)

G. Kingston, Compliance Manager (NHY)

• J. J. Warnock, Nuclear Quality Manager (NHY)

US Nuclear Regulatory Commission

• A. C. Cerus, Senior Resident Inspector

• D. Rascitto, Resident Inspector

• 0cnotes those present at exit interview on June 27, 1986 2.0 Licensee Action on Previous Inspection Findings (Closed) Unresolved Item 50-443/86-19-02, "0 mission of sign offs in com-pleted tests" Scope During inspection 50-443/86-19 it was found that some sections in pre-operational test procedures PT-34.1 and PT-37.2 (see ref I and 2) did not have sign offs by responsible test personne References (1) PT-34.1, "New Fuel Handling Equipment", Rev. 1, approved by the Joint Test Group (JTG) Jan 10, 1986, test results approved by JTG on April 18, 1986 (2) PT-37.2, " Containment type Band C Tests, approved by JTG on Jan 10, 1986, test results approved on April 18, 198 (3) Inspection Report 50-443/86-1 _.,

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s Discussion In both cases the sign offs were deleted purposely because sign offs for the detailed actions were covered elsewhere in the reports. In the case of PT-37.2, the licensee will add a note that initials for section 4 were reviewed _for log entrie In the case of PT 34.1, there was an option to be considered to either do the test for the cranes or to supply the ven-dor's test data. The latter option was selected by the licensee and, therefore, no initials would be required for the other option. The in-spector felt that the basic requirements had been met. There should be no reason not to sign off for it under the test section. The licensee agreed to do that and to obtain JTG approval for the action taken in both case Findings This item is hereby close .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 the attributes identified in Inspection Report 50-443/86-19 Findings No noncompliances were identified by the inspector within the scope of this inspectio .2 Test Result Evaluation Scope 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 for evaluating completed preoperational tests in order to assure their technical and administrative adequacy.

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Discussion The test results were reviewed for the attributes identified in Inspection Report 50-443/86-19. A test change deleted sections and 6.7 entirely in PT-1 Backup air had not been completed ye The test will now be done under 1 PT-47, "The Backup Gas Supply Verification Test". The preoperational containment integrated leak rate test (CILRT) was conducted in accordance with procedure and was concluded on March 19, 1986. The purpose of the test was to demon-strate the acceptability of the containment leak rate at or above the design basis accident pressure of the containment, approximately 6 psi The inspector reviewed the summary technical report submitted to the NRC by the licensee entitled " Reactor Containment Building Intergrated leak Rate Test" dated March 1986. The results therein indicate a successful 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> CILRT. The calculated leak rate based on the mass point method of analysis is 0.052 wt. %/ day of containment air. At the 95% Upper Confidence Level (UCL) the leakage is 0.055 wt. %/ da With the addition of leakage for penetrations in use for the conduct of the test the total integrated leak rate at UCL is 0.058 wt. %/ da This is below the allowable leak rate of .75 L, which is 0.1125 w %/ day for Seabrook Unit The 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> CILRT was followed by a successful Verification Leak Rate Test (VLRT). This test is designed to check the accuracy of the CILRT instrumentation. A leakage equivalent to 0.160 wt. %/ day was superimposed on the existing containment leakage using a rotamete CILRT leak rates were then calculated for 4 3/4 hours. At the end of the VLRT, the test was found to be successful. The VLRT measurements were within the 0.25 L, acceptance criteri Findings No discrepancies or unacceptable conditions were noted in the review of the test results for these procedure .3 Test Exceptions Scope The inspector reviewed the status of safety significant open items and the licensees progress on closing items since the last inspection (Report No. 50-443/86/37).

Findings No violations of NRC requirements weie identifie _ _ ._

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4.0 Independent Inspection Effort Scope Determine the status and extent of the response to IE Information Notice 85-96 on the installation and removal of temporary strainers. Determine what administrative control exists for the removal of these strainers after testin References (1) PSNH Company business memorandum " Temporary Strainers" Walsh to G. Kametal, dated January 25, 198 (2) Action Correspondence Report No.36-002, dated Feb 9, 198 (3) Work Request 17837, WR-SI-0238, for Safety Inspection System, removal

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of suction strainer of pump SI-P-6A, approved December 17, 1985 (4) Work Request 17838, WR-SI-0239, for Safety Inspection System, removal of suction stranier of pump SI-P-6B, approved December 17, 198 Discussion A review of the administrative measures governing the control of the temporary strainers revealed the following:

The Process and Instrument Diagram, produced by the architect engineer, United Engineers, only identifies temporary strainers specified by them. These strainers have a slanted scree *

There also is a basket type strainer which are available to Startup (STD) for their use, at their disgression. The generic flushing procedures (GTCs) identify where these basket strainers are to be installe *

The detail flush package for the system will specify, via Work Req-uests (see ref. 2 and 3), where the temporary strainers are to be installe *

There is a separate sign-off on the flush package to restore the system after clearin *

The work requests of the clearing package are entered into the In-complete Items List (IIL). The work request for the permanent spool installation will take the temporary strainer back out agai *

The turnover package (BIPS) would have identified what temporary strainer's were installed by construction.

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The IIL will track the removal of all temporary strainers via work request Findings The administrative control of temporary suction strainers of pumps exists and should be adequate. The inspector will follow up with a review of the implementation of this administrative control system in a future inspec-tio .0 QA/QC Interface Scope The participatio.i of the YAEC Field QA Group in the witnessing of the test for the 120 VAC Vital Instrument Power Supply (PT-32), Emergency Diesel Generator Reliability (PT-33.2); Containment Type B and C Tests (PT-37.2A); Post Accident Handling System (AT-10.5); Fuel Handling and Transfer Equipment (PT-34.2); Emergency Feedwater System Logic Verifi-cation (PT-14.4); Containment Isolation System (PT-21); Containment Air Recirculation System (PT-26); Hydrogen Recombiners (PT-25.2); Backup Hydrogen Gauge (PT-25.3); Cooling Tower System (PT-15.1); Service Water Pumps and Cooling Tower Actuation (PT-15.2); and ther pts and ATs, was evaluate Discussion In continuation of the assessment of QA/QC involvement with the preoperat-ional 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. None of these surveillances indicated any deficiencie Findings No noncompliances were observed within the scope of this inspectio .0 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. For the items closed during this inspection period please refer to section 2 of this repor .0 Exit Interview At the conclusion of the site inspection, on June 27, 1986, an exit inter-view was conducted with the licensee's senior site representatives (denoted in Section 1). The findings were identified and previous in spection items were discusse .

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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 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 restriction .

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I ATTACHMENT A to 50-443/86-40 Test Procedure Reviews Proc. No. Title Rev. No. Appr. Date 1 PT-14.4 Emergency Feedwater System 1 5-30-86 Valve Logic Verification 1 PT-19.2 Reactor Protection System 0 6-20-86 Response Time Evaluation

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ATTACHMENT B to 50-443/86-40-Test Results Evaluation Test-Results Proc. No. Title Rev. No Approval 1 PT-16.4 Emergency Feedwater System 1 6-26-86 Valve Logic Verification 1 PT-19.1 Reactor Protection System 0 8-30-85 PT-37.1 Containment Type A Test 1 6-16-86

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ATTACHMENT C to 50-443/86-40 Review of Surveillance Reports (SR) Issued by YAEC (FQAG)

Sr No. Test Proc. Observed T.P. Title Rpt. Date SR Y-1899 1 PT-32 120 VAC Vital Inst Power Supply Y-1914 1 PT-32 Ditto 6-12-86 Y-1936 1 PT-32 Ditto 6-17-86 Y-1728 1 PT-3 EDG Reliability Tests 5-14-86 Y-1737 1 PT-3 Ditto 5-16-86 Y-1755 1 PT-3 Ditto 5-17-86 Y-1766 1 PT-3 Ditto 5-19-86 Y-1803 1 PT-3 Ditto 5-27-86 Y-1869 1 PT-3 Ditto 6-6-86 Y-1930 1 PT-3 Ditto 6-16-86 Y-1870 1 PT-3 Ditto - 6-06-86 Y-1729 1 PT-37.2A Rx Content Type Band C 5-14-86 leakage rate test Y-1751 1 PT-37.2A Rx Content Type Band C 5-19-86 leakage rate test Y-1804 1 PT.37.2A Ditto 5-27-86 Y-1825 1 PT.37.2A Ditto 5-30-86 Y-1978 1 PT.37.2A Ditto 6-24-86 Y-1953 1 PT.37.2A Ditto 6-19-86

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Appendix C 2

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Sr N Test Proc. Observed T.P. Title Report Date Sr Y-1991 1 AT-1 Post Accident Sampling 6-25-86 Y-1992 1 AT-1 Instr. and Service Air 6-25-86 Containment Y-1897 1 PT-3 Fuel Handling and 6-10-86 Transfer Equipment Y-1894 1 PT-3 Ditto 6-10-86 Y-1971 1 AT-16 Spent Resin Sluice 6-23-86 System Y-1986 1 PT-1 Emergency Feedwater 6-25-86 System Logic Verification Y-1871 1 AT-3 Mile Radius Radio 6-6-86 Communcation System Sr N Test Proc. Observed T.P. Title Report Date Sr Y-1778 1 AT-1 Fire Pump Flow Ca Testing Y-1721 1 AT-1 Halon Systems Testing 5-13-86 Y-1635 1 PT-21 Containment Isolation 4-30-86 System Y-1484 1 AT-22 Containment Purge System 4-15-86 Y-1457 1 PT-26 Containment Air Revise 4-11-86 System Y-1424 1 PT-2 Hydrogen Recombiner 4-7-86 Y-1423 1 PT-2 Backup Hydrogen Purge 4-7-86 Y-1588 1 PT-1 Service Water Cooling 4-24-86

. Tower Y-1618 1 PT-1 Service Water Pumps and 4-28-86 Tower Actuation Y-1756 1 PT-1 Service Water Flow 5-19-86 Balancing Y-1696 1 PT-15.11 Service Water Cooling 5-10-86 Tower, Portable Makeup Pump

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Appendi< C 3 i

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