IR 05000410/1986027

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Safety Insp Rept 50-410/86-27 on 860519-23.No Violations Noted.Major Areas Inspected:Preoperational Test Witnessing & Results Evaluation Review,Independent Verification & Plant Tours
ML17055B840
Person / Time
Site: Nine Mile Point Constellation icon.png
Issue date: 06/12/1986
From: Eselgroth P, Marilyn Evans
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML17055B838 List:
References
50-410-86-27, NUDOCS 8606190431
Download: ML17055B840 (10)


Text

U.S.

NUCLEAR REGULATORY COMMISSION

REGION I

Report No.

50-410/86-27 Oocket No.

50-410 License. No.

CPPR-112 Licensee:

Nia ara Mohawk Power Cor oration 300 Erie Boulevard Nest S racuse New York 13202 Facility Name:

Inspection At:

Nine Mile Point Nuclear Station Unit 2 Scriba New York

Inspector Evans, ctor Engineer Jj 8(

date Approved By:

P. Eselgrot Chief, Test Programs Section, d

e Ins ection Summar:

Ins ection on Ma 19-23 1986 Re ort No. 50-410/86-27 Areas Ins ected:

Routine, unannounced inspection by one region based inspector of preoperational test witnessing, preoperational test results evaluation review, gA interface with the preoperational test program, independent verification and plant tour s.

Results:

No violations were identified.

NOTE:

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

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DETAILS 1.0 Persons Contacted

~Nia ara Mohawk Power Cor oration

  • R G

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Abbott, Station Superintendent Afflerbach, Startup Manager Beckham, Manager, Quality Assurance (QA) Projects Drake, Startup Special Projects Supervisor (SWEC)

Eddy, Site Representative Griffith, Site Licensing Engineer Hansen, Manager, Nuclear Quality Assurance Operations Lee, Special Projects Matlock, Special Projects Perkins, General Superintendent Proios, Test Engineer Ray, Manager, Special Projects Weakley, Special Projects Other NRC Personnel R'.

C Gramm, Senior Resident Inspector, Construction Finkel, Lead Reactor Engineer Petrone, Lead Reactor Engineer

  • Denotes those present at the exit meeting conducted on May 23, 1986.

The and inspector also contacted other members of the licensee's technical QA staff.

2.0 Preo erational Test Witnessin 2.1

~Sco e

Testing witnessed by the inspector included the observations of over-all crew performance stated in Paragraph 4.0 of Inspection Report 50-410/86-14.

2.2 Discussion During the period of May 15-19, 1986, the licensee conducted Loss of Offsite Power ( LOOP) Testing per preoperational test procedure N2-POT-300,

"Loss of Offsite Power/ECCS",

Revision 1, approved May 6, 1986.

On May 19, 1986, the inspector witnessed a retest of Section 4.3, "Sequential LOCA/LOOP with all three ECCS Divisions Available and DG Reload after engine temperature equilibrium".

All testing was conducted in accordance with the attributes of Paragraph 4.0 of Inspection Report 50-410/86-14.

The inspector observed continuous QA coverage during LOOP testin.3

~Findin s

No unacceptable conditions were observed.

3.0 Prep erational Test Results Evaluation Review 3.1

~Sco e

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 require-ments and to verify that uniform criteria were being applied for evaluation of completed test results in order to assure technical and administrative adequacy.

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 procedure, acceptance criteria, performance verification, recording conduct of the test, gC inspection records, restoration of system to normal after test, inde-pendent verification of critical steps or parameters, identification of personnel conducting and evaluating, test data, and verification that the test results have been approved.

N2-POT-19-1, Instrument and Service Air, Revision 1, results approved April 24, 1986.

N2-POT-60, Drywell Cooling, Revision 1, results approved May 2, 1986.

N2-POT-33, High Pressure Core Spray, Revision 1,.results approved May 12, 1986.

The inspector also conducted a preliminary review of N2-POT-300, Loss of Offsite Power/ECCS, Revision 1, which was completed May 19, 1986 and has not yet been reviewed and approved by the licensee.

3.2 'iscussion N2-POT-300 During preliminary results review of N2-POT-300, the inspector dis-cussed various aspects of the testing with the System Test Engineer (STE).

The STE explained the problems encountered during testing, the resolution of these problems and the method of recording data.

The only significant problem noted by the inspector was the sequenc-ing times were not within specification for the LOCA/LOOP with all three ECCS divisions available.

All major safety related loads were properly shed from their respective busses, however, several of the breaker sequencing times were not within specification.

The licensee

issued Problem Report (PR) 804477, requesting engineering to evaluate the breaker closing times.

The inspector will further review this item during a subsequent NRC inspection, following licensee approval of the completed procedure.

3.3

~Findin s

During the above results evaluation review, no violations were iden-tified.

However, the inspector questioned the licensee concerning the lack of adequate documentation in the approved preoperational test packages of deficiencies which were open at the time of test results approval.

Also, the inspector questioned the licensee's planned method of documenting in the preoperational test package the final closure of these open deficiencies.

The licensee acknowledged the inspectors concerns and agreed to include a list of deficiencies, the status of the deficiencies and the supporting closure documenta-tion in all preoperational test packages.

This item will remain unresolved (50-410/86-27-01)

pending licensee action.

4.0 A Interface with the Prep erational Test Pr~oram'.1 Discussion The inspector reviewed several recent Nuclear Quality Assurance Sur-veillance Reports (QASg) regarding various activities of the licen-see's startup department.

The following QASR's were reviewed:

QSAR 86-10368, Test Results Review of N2-POT-33, High Pressure Core Spray, review completed April 29, 1986.

The QA inspector used QA checklist SQA-S-145-86, Revision 1, to check various attributes of the completed procedure.

All QA comments were adequately resolved.

QSAR-86-10364, Surveillance of the performance of POT prerequisites for N2-POT-92-3, Power Range Monitoring, conducted April 27, 1986.

The QA inspector used QA prerequisite checklist SQA-S-002-85, Revision 0, to check various attributes of the above procedure prior to actual testing.

The QA inspector noted that the FSAR amendment referenced in the POT did not reflect the current document revision.

The QA inspector reviewed N2-POT-92-3 test results record copy on May 22, 1986 and verified the FSAR amendment to be properly updated.

All other prerequisites were satisfactorily accompli shed.

QASR-86-10390, Test Results Review of N2-POT-19-1, Instrument and Service Air, completed on May 4, 1986.

The QA inspector found the results to be in compliance with QA checklist SQA-S-145-8 gASR-86-10380, Surveillance of preoperational test N2-POT-31, Revision 2, Residual Heat Removal System, conducted on April 19, 1986.

The gA inspector observed the removal of system startup strainers from RHR loops A, B and C per deficiency reports (DR's) 02625, 02526 and 02627.

RHR pump curves for each RHR loop were verified.

4.2

~Findin s

.

No unacceptable conditions were identified.

5.0 Inde endent Calculations The inspector performed independent pump head and net positive suction head (NPSH) calculations during the results evaluation review of N2-POT-33 discussed in paragraph 3.0.

5.1

~F1ndin s

No unacceptable conditions were noted.

6.0 Plant Tours The inspector made several tours of various areas of the facility to observe work in progress, housekeeping, cleanliness controls, status of construction and preoperational testing activities.

6.1

~Findin s

No unacceptable conditions were noted.

7.0 Unresolved Item Unresolved items are matters about which more information is required in order to ascertain whether they are acceptable, an item of noncompliance or a deviation.

The unresolved item identified during this inspection is discussed in Paragraph 3.3 of this report.

8.0 Exit Interview A management meeting was held at the conclusion of the inspection on Hay 23, 1986, to discuss the inspection scope, findings and observations as detailed in this report (see Paragraph 1 for attendees)

.

No written information was provided to the licensee at any time during this inspec-tion.

The licensee indicated that no proprietary information was con-tained in the scope of this inspection.