IR 05000410/1987006

Insp Rept 50-410/87-06 on 870210-13.No Violations Noted. Major Areas Inspected:Preoperational Test Results Review, Overall Power Ascension Test Program,Qa/Qc Interfaces, Independent Verifications & Facility Tours

ML20207S592
Person / Time
Site:	Nine Mile Point
Issue date:	03/10/1987
From:	Eselgroth P, Marilyn Evans, Wink L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20207S590	List: IR 05000410/1987006 ML20207S589
References
50-410-87-06, 50-410-87-6, NUDOCS 8703200072
Download: ML20207S592 (7)

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U.S. NUCLEAR REGULATORY COMMISSION

REGION I

Report No. 50-410/87-06 Docket N License No. NPF-54 Licensee: Niagara Mohawk Power Corporation 301 Plainfield Road Syracuse, New York 13212 Facility Name: Nine Mile Point Nuclear Station, Unit 2

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Inspection At: Scriba, New York Inspection Conducted: February 10-13, 1987 Inspectors: w N2 h Engineer .date, M.Evan}ReactkoJU h }& 3MQ L." Wink, Rea tor Enginef r daj'e /

Approved by: [ f// / 3//d/f 7

' date P.EselgrotyChief,TestProgramsSection OB, DRS Inspection Summary: Inspection of February 10-13, 1987 (Report No. 50-410/87-06).,

Areas Inspected: Routine, unannounced inspection by two region based inspectors of licensee actions on previous inspection findings, preoperational test results review, overall power ascension test program, power ascension test results evaluation, QA/QC interfaces, independent verifications, and plant tour Results: No violations were identifie NOTE: For acronyms not defined, refer to NUREG-0544 " Handbook of Acronyms and Initialisms."

8703200072 B70312 PDR ADOCK 05000410 0 PDR

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Details 1.0 Persons Contacted Niagara Mohawk Power Corporation G. Carlisle, Lead STD & A Engineer

• J. Conway, Power Ascension Manager

• P. Eddy, Site Representative, New York State, PSC

• L. Fenton, Audit Lead

• W. Hansen, Manager, Nuclear Quality Assurance (QA) Operations

• M. Jones, Superintendent Operations

• L. Lagoe, Unit Instrumentation and Controls Supervisor

• P. MacEwan, Site Representative, New York State Electric and Gas

• T. Newman, Supervisor, Operations QA Surveillance

• T. Perkins, General Superintendent

• A. Pinter, Site Licensing Engineer

P. Wilde, Supervisor, QA Surveillance - Unit 2 Other NRC Personnel

• Cook, Senior Resident Inspector

• C. Msrschall, Resident Inspector

• Schmidt, Resident Inspector

• Denotes those present at exit meeting on February 13, 1987.

The inspectors also contacted other members of the licensee's technical, QA and operations staf .0 Licensee Actions on Previous Inspection Findings (Closed) Deviation (410/86-33-01). This item deals with the licensee's failure to Joint Test Group (JTG) review the results of preliminary test MD.0100.A03, " Standby Diesel Generator Reliability Test." The inspector reviewed the completed test package and verified that the test results were reviewed and found acceptable by the JTG (meeting #86-153) on August 26, 1986. This item is close Closure of this item and the completion of the preoperational test results review discussed in paragraph 3.0 constitute final closecut of the NRC Nine Mile Point Unit 2 preoperational test progra .0 Preoperational Test Results Review 3.1 Scope The completed test procedures listed below were reviewed during this inspection to verify that adequate testing had been conducted to satisfy regulatory guidance, licensee commitments and FSAR

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requirement These preoperational tests were completed after the issuance of an operating license because the licensee had been granted an exemption permitting completion of these systems to be delayed until initial criticalit N2-P0T-23-1, " Turbine EHC-Electronic," System declared operational January 29, 198 N2-P0T-23-2, " Turbine EHC -

Hydraulic," System declared operational January 29, 198 N2-POT-42, "Off-Gas System," Revision 2, System declared operational January 28, 198 N2-P0T-1-2, " Main Steam Isolation Valves," Revision 0, Station Operations Review Committee (SORC) approved January 22, 198 N2-POT-1-3, " Main Steam Isolation Valves," Revision 0, SORC approved January 23, 198 N2-POT-62, "DBA Hydrogen Recombiners," System declared operational January 30, 198 .2 Discussion The inspector reviewed the test results and verified the licensee's evaluation of test results by review of test changes, test exceptions, test deficiencies, "As-Run" copy of the test procedures, acceptance criteria, performance verification, recording conduct of test, QC inspection records, restoration of system to normal after test, independent verification of critical steps or parameters, identification of personnel conducting and evaluating test data, and verification that the test results have been approve For each of the above preoperational tests the inspector reviewed the applicable sections of the Nine Mile Point Unit 2 Final Safety Analysis Report and Regulatory Guide 1.68, " Initial Test Programs for Water Cooled Nuclear Power Plants," Revision 2, August 1978, and verified that licensee testing commitments and all acceptance criteria for each system were satisfie In addition, the inspector discussed any questions concerning the test results with the applicable test engineer for each syste All questions were adequately answere Preoperational tests N2-POT-1-2 and N2-POT-1-3 were conducted to test the main steam isolation valves (MSIVS) following modification 86-118, which replaced the original valve actuator with hydraulic actuator and modification 87-006, which revised the MSIV Logic to comply with the requirements of 10CFR50, Appendix A, General Design

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Criterion 21 and of IEEE Standard 279. The inspector reviewed these test results and verified that all the MSIV'S fast closed within the acceptance criteria limit of 3-5 second .3 Findings No violations were identified within the scope of'this revie .0 Power Ascension Test Program (PATP)

4.1 References

Regulatory Guide 1.68, Revision 2, August 1978 " Initial Test Program for Wator Cooled Nuclear Power Plants."

ANSI N18.7-1976 " Administrative Controls and Quality Assurance for Operations Phase of Nuclear Power Plants."

Nine Mile Point Unit 2 (NMP-2) Technical Specifications, Revision 0, October 31, 198 *

NMP-2 Final Safety Analysis Report (FSAR) Chapter 14 " Initial Test Program."

NMP-2 Safety Evaluation Report

, NMP-2 AP-1.4, Startup Test Phase, Revision 2 4.2 Overall Power Ascension Test Program The inspector held discussions with the Power Ascension Manager (PAM)

and the Lead Startup Test, Design and Analysis Engineer and other members of the PATP staff to assess the status of the test results evaluation process, preparation _and approval of test procedures, and the overall readiness to begin low power testin All test results from open vessel testing have been reviewed and formally accepted by licensee management. All test procedures required for low power testing have received formal review and approval and the balance of the required PATP procedures are in their final review and approval cycl All test engineers for the power ascension program are on-site and have received formal trainin The inspector reviewed site administrative procedures AP-1.4, Startup Test Phase, Revision 2, approved October 30, 1986, and AP-8.4, Procedure for Control and Calibration of Equipment Used in Tests and Inspections, Revision 5, approved October 28, 1986, to assess the adequacy of these administrative controls for PATP activitie The procedures were found to contain acceptable administrative controls for the conduct of PATP activitie . _ . . .- _ . - . , .

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The inspector held discussions with the Power Ascension Manager and Lead Startup Test, Design and Analysis Engineer concerning confor-mance to Regulatory Guide 1.6 In particular, the inspector ,

inquired about the scope of single reactor recirculation loop testing. Nine Mile Point Unit 2 Technical Specifications allow plant startup and continued operations up to 70% of rated thermal power with a single reactor recirculation loop in operatio Regulatory Guide 1.68, Appendix A, Section 5, Power-Ascension Tests, states that appropriate consideration should be given to testing at the extremes of possible operating modes and specifically mentions single loop operation. _The inspector noted that the description- of the proposed test program in Chapter 14 of the FSAR does not expiicitly discuss or describe single loop operations testing. The PAM requests time to prepare a complete response to this concern. Pending receipt of the licensee's response, and evaluation by the NRC, the adequacy of the planed testing for single reactor recirculation loop operations will remain unresolved (410/87-06-01).

4.3 Power Ascension Test Results Evaluation 4. Scope The power ascension test results listed in Attachment A were evaluated for the attributes identified in Inspection Report 50-410/86-6 . Discussion The test results listed in Attachment A had been previously reviewed and evaluated for technical and administrative adequacy (see Inspection Reports 50-410/86-64 and 50-410/86-68). During this inspection the evaluation focused on the licensee's review and approval process including quality assurance review and formal management acceptance of the test result . Findings No deficiencies were identifie .0 QA Interface with the Power Ascension Test Program The inspector met with the QA supervisor for Startup/ Operations Surveillance Unit 2 to review the plans for the power ascension surveillance progra Plans call for 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> coverage of the power ascension program and have identified specific tests for which detailed surveillance checklists have been prepared. All power ascension test procedures and test results will be subject to QA review and approval. Specific QA engineers have been assigned responsibility for individual power ascension test The

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inspector found the planned surveillance program to be well organized and comprehensiv During the review of the test results from open vessel testing the inspector verified that the results had been reviewed and approved by QA.

L 5.1 Findings No deficiencies were identifie .0 Independent Verifications The inspector independently verified that all acceptance criteria were satisfied during review of the preoperational test results as discussed in paragraph .0 Plant Tours The inspector made several tours of the reactor building, turbine building and control building to observe work in progress, general housekeeping and cleanliness controls, and overall status of the facility to support power ascension testin .1 Findings No unacceptable conditions were identifie .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. An unresolved item identified during this inspection is discussed in paragraph .0 Exit Interview A management meeting was held at the conclusion of the inspection on February 13, 1987, to discuss the inspection scope, findings and observations as detailed in this report (see Paragraph I for attendees).

No written information was provided to the licensee at any time during this inspectio The licensee did not indicate that any proprietary information was contained within the scope of this inspectio ~

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ATTACHMENT A-Power Ascension Test Results Evaluated N2-SUT-1-0V. Chemical and Radiochemical - Open Vessel Testing, Revision 2, completed October 31, 1986, results accepted February 6, 1987 N2-SUT-2-0V Radiation Measurements - Open Vessel, Revision 1, completed November 18, 1986, results accepted February 6, 1987 N2-SVT-3-0V Fuel Load, Revision 2, completed November 15, 1986, results accepted February 6, 1987 N2-SVT-5-0V Control Rod Drive System, Revision 2, completed November 25, 1987, results accepted February 6, 1987 N2-SUT-13-0V Process Computer - Test Condition Open Vessel, Revision 4, completed December 10, 1986, results accepted February 6, 1987

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