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U.S. flVCLEAR REGULATORY COMMISSION
U.S. flVCLEAR REGULATORY COMMISSION


==REGION I==
==REGION I==
Report No. 50-410/86-64 Docket No. 50-410 License No. NPF-54 Licensee: Niagara Mohawk Power Corporation 300 Erie Boulevard, West Syracuse, New York 13202 Facility Name: Nine Mile Point Nuclear Station, Unit 2 Inspection At: Scriba, New York Inspection Conducted: November 17 - 21, 1986 Inspector: , D an/ /2 - / 2 - Bf M. Evant,, Repctor' eer date Approved by: Dri//ot m' /2 - /2 - 84 fu D. FloreY Cpief, f date
Report No. 50-410/86-64 Docket No. 50-410 License No. NPF-54 Licensee: Niagara Mohawk Power Corporation 300 Erie Boulevard, West Syracuse, New York 13202 Facility Name: Nine Mile Point Nuclear Station, Unit 2 Inspection At:
/ Test Programh Sec Wn, 08, DRS Inspection Summary: Inspection on November 17 - 21, 1986 (Report No. 50-410/86-64).
Scriba, New York Inspection Conducted: November 17 - 21, 1986 Inspector:
D an/
/2 - / 2 - Bf
,
M. Evant,, Repctor'
eer date Approved by:
Dri//ot m'
/2 - /2 - 84 fu D. FloreY Cpief, f
date
/
Test Programh Sec Wn, 08, DRS Inspection Summary:
Inspection on November 17 - 21, 1986 (Report No. 50-410/86-64).
 
Areas Inspected: Routine unannounced inspection by one region based inspector of power ascension test results evaluation, power ascension test witnessing, surveillance procedure review, QA/QC interfaces, independent measurements and verifications, and plant tours and meetings.
 
Results: No violations were identified.


Areas Inspected: Routine unannounced inspection by one region based inspector of power ascension test results evaluation, power ascension test witnessing, surveillance procedure review, QA/QC interfaces, independent measurements and verifications, and plant tours and meeting Results: No violations were identifie Note: For acronyms not defined, refer to NUREG-0544 " Handbook of Acronyms and Initialisms."
Note:
For acronyms not defined, refer to NUREG-0544 " Handbook of Acronyms and Initialisms."
 
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1.0 Persons Contacted Niagara Mohawk Power Corporation
1.0 Persons Contacted Niagara Mohawk Power Corporation
* Boyle, Nuclear Compliance and Verification
*M. Boyle, Nuclear Compliance and Verification
*J. Conway, Power Ascension Manager
*J. Conway, Power Ascension Manager
*W. Hansen, Manager, Nuclear Quality Assurance (QA), Operations
*W. Hansen, Manager, Nuclear Quality Assurance (QA), Operations
*M. Jones, Superintendent Operations J. McKenzie, Quality Surveillance
*M. Jones, Superintendent Operations J. McKenzie, Quality Surveillance
*T. Newman, Supervisor, Operations Surveillance
*T. Newman, Supervisor, Operations Surveillance
*J. Perry, Vice President, QA
*J. Perry, Vice President, QA
*A. Pinter, Site Licensing Engineer
*A. Pinter, Site Licensing Engineer
*P. Wilde, QA Surveillance Supervisor Other NRC Personnel
*P. Wilde, QA Surveillance Supervisor Other NRC Personnel
* Cook, Senior Resident Inspector
*W. Cook, Senior Resident Inspector
* Schmidt, Resident Inspector
*W. Schmidt, Resident Inspector
* Denotes those present at the exit meeting on [[Exit meeting date::November 21, 1986]].
* Denotes those present at the exit meeting on [[Exit meeting date::November 21, 1986]].
The inspector also contacted other members of the licensee's technical, QA and Operations staf .0 Power Ascension Test Program References
The inspector also contacted other members of the licensee's technical, QA and Operations staff.
*
 
2.0 Power Ascension Test Program References
*
Regulatory Guide 1.68, Revision 2, August 1978 " Initial Test Program for Water Cooled Nuclear Power Plants".
Regulatory Guide 1.68, Revision 2, August 1978 " Initial Test Program for Water Cooled Nuclear Power Plants".


ANSI N18.7-1976 " Administrative Controls and Quality Assurance for Operations Phase of 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, 1986.


*
NMP-2 Final Safety Analysis Report (FSAR) Chapter 14 " Initial Test Program'.
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 Safety Evaluation Repor Overall Power Ascension Test Program Initial Fuel Loading was completed on November 15, 1986. At the time of this inspection open vessel testing was proceeding smoothly with startup tests N2-SUT-05-0V, CRD and N2-SUT-13-0V, Process Computer remaining to be +
 
complete _ . _
Overall Power Ascension Test Program Initial Fuel Loading was completed on November 15, 1986. At the time of this inspection open vessel testing was proceeding smoothly with startup tests N2-SUT-05-0V, CRD and N2-SUT-13-0V, Process Computer remaining to be
+
completed.
 
_. _


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.
*
* 2.1 Power Ascension Test Results Evaluation Scope The power ascension test results discussed below were reviewed to verify that:
--
The test was performed in accordance with a current, approved procedure.
 
--
Test changes were approved in accordance with administrative procedures.
 
--
Test changes are annotated in the procedure and completed, if appropriate.
 
The basic objectives of the test were met.
 
--
--
Test deficiencies are documented, as required.
 
--
Test deficiencies were resolved, accepted by management and retests completed, if required.
 
System or process changes necessitated by test deficiencies have
--
been properly documented and reviewed.
 
--
Test. deficiencies which constitute reportable occurrences have been properly reported.


2.1 Power Ascension Test Results Evaluation Scope The power ascension test results discussed below were reviewed to verify that:
--
--
Required test data has been obtained and is within tolerances.
The test was performed in accordance with a current, approved procedur Test changes were approved in accordance with administrative procedure Test changes are annotated in the procedure and completed, if appropriat The basic objectives of the test were me Test deficiencies are documented, as require Test deficiencies were resolved, accepted by management and retests completed, if require System or process changes necessitated by test deficiencies have been properly documented and reviewe Test. deficiencies which constitute reportable occurrences have been properly reporte Required test data has been obtained and is within tolerances.


~
~
--
--
Individual test steps and data sheets have been properly initialed and date An engineering evaluation of the test data has been performe Test results are evaluated against established acceptance criteri Review and acceptance of test results has been documente Tests results have been reviewed by Quality Assurance or other Independent Organizatio Test results have been approved by appropriate managemen Discussion
Individual test steps and data sheets have been properly initialed and dated.
-
 
--
An engineering evaluation of the test data has been performed.
 
Test results are evaluated against established acceptance
--
criteria.
 
--
Review and acceptance of test results has been documented.
 
--
Tests results have been reviewed by Quality Assurance or other Independent Organization.
 
Test results have been approved by appropriate management.
 
--
Discussion
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N2-SUT-1-0V, Chemical and Radiochemical
N2-SUT-1-0V, Chemical and Radiochemical
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The inspector reviewed the preliminary test results package and noted that a test exception had been written for a level 1 acceptance criteria concerning condensate demineralizer effluent dissolved 02 concentration. The 0 2concentration was out of specification high at 8300 ppb (requirement of 20-200 ppb). The licensee's resolution was to accept as is because the 20-200 ppb requirement applies at operating conditions only. Five additional test exceptions not related to acceptance criteria were identified and properly dispositione N2-SUT-2-0V, Radiation Measurements The inspector reviewed the preliminary test results package and verified that all acceptance criteria were satisfie N2-SUT-3-0V, Fuel Loading The inspector independently evaluated the preliminary test results including the 1/M plots maintained during the loading and the partial core shutdown margin test. In addition, the inspector reviewed portions of video tapes of the core verifi-cation conducted by the licensee following loading of the 362nd fuel bundle and following loading of the last fuel bundle (764th). The licensee verified proper fuel bundle orientation and location as documented in N2-RPSTP-5, Core Verificatio Fuel loading began on November 2, 1986 and the last bundle was loaded on November 15, 1986. All acceptance criteria were satisfied. One test exception was generated for having the "C" SRM bypassed while loading fuel bundles into the "C" quadran This is discussed further in the Senior Resident Inspector's inspection report (50-410/86-56).
-
The inspector reviewed the preliminary test results package and noted that a test exception had been written for a level 1 acceptance criteria concerning condensate demineralizer effluent dissolved 0 concentration. The 0 concentration was out of
 
2 specification high at 8300 ppb (requirement of 20-200 ppb). The licensee's resolution was to accept as is because the 20-200 ppb requirement applies at operating conditions only.
 
Five additional test exceptions not related to acceptance criteria were identified and properly dispositioned.
 
-
N2-SUT-2-0V, Radiation Measurements The inspector reviewed the preliminary test results package and verified that all acceptance criteria were satisfied.


-
-
N2-RPSTP-1, Shutdown Margin Test Due to the occurrence of several spurious neutron monitoring system scram signals, the licensee performed this test to demonstrate sufficient full core shutdown margin. Once demon-strated, the RPS shorting links were reinstalled, therefore restoring RPS coincident logic and eliminating the spurious scram signal The inspector reviewed the results of this test and verified that sufficient shutdown margin was demonstrate >
N2-SUT-3-0V, Fuel Loading The inspector independently evaluated the preliminary test results including the 1/M plots maintained during the loading and the partial core shutdown margin test.
Findings No unacceptable conditions were identifie ,
 
l
In addition, the inspector reviewed portions of video tapes of the core verifi-cation conducted by the licensee following loading of the 362nd fuel bundle and following loading of the last fuel bundle (764th). The licensee verified proper fuel bundle orientation and location as documented in N2-RPSTP-5, Core Verification.
 
Fuel loading began on November 2, 1986 and the last bundle was loaded on November 15, 1986. All acceptance criteria were satisfied. One test exception was generated for having the "C" SRM bypassed while loading fuel bundles into the "C" quadrant.
 
This is discussed further in the Senior Resident Inspector's inspection report (50-410/86-56).
 
-
N2-RPSTP-1, Shutdown Margin Test Due to the occurrence of several spurious neutron monitoring system scram signals, the licensee performed this test to demonstrate sufficient full core shutdown margin. Once demon-strated, the RPS shorting links were reinstalled, therefore restoring RPS coincident logic and eliminating the spurious scram signals.
 
The inspector reviewed the results of this test and verified that sufficient shutdown margin was demonstrated.
 
>
Findings No unacceptable conditions were identifie,
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*
*


2.2 Power Ascension Test Witnessing-Scope The inspector witnessed portions of the power ascension test discussed below. The performance of this test was witnessed to verify that:
2.2 Power Ascension Test Witnessing-Scope The inspector witnessed portions of the power ascension test discussed below. The performance of this test was witnessed to verify that:
--
--
The current, approved revision of the test procedure was available and in use by all participant The minimum crew requirements, as defined in the approved procedure and technical specifications, were being me Required prerequisites and initial conditions were establishe Test equipment was calibrated and operated in accordance with procedur The procedure was technically adequate and appropriate to the circumstance Crew performance was correct and timel Coordination of test related activities was adequat A preliminary analysis of all data collected was expeditiously performed following completion of the tes The test was performed in accordance with all administrative requirement Discussion
The current, approved revision of the test procedure was available and in use by all participants.
-
 
N2-SUT-5-0V, Centrol Rod Drive System This startup test includes friction, functional and scram time testing of all control rod drives (CRD's) at a reactor pressure of 0 psi ,
--
The inspector witnessed performance of section 6.2, Friction Testing, for CRD's 30-07, 30-03 and 26-03. The overall test crew performance was satisfactory. The inspector observed test equipment set up for each rod, initiation of testing for each rod and data reduction following the testing of each rod. All test results were within acceptance criteria limit ._ . . ._
The minimum crew requirements, as defined in the approved procedure and technical specifications, were being met.
      .
 
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Required prerequisites and initial conditions were established.


      '
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Findings No violations were identifie .0 Surveillance Procedure Review Scope The inspector reviewed the surveillance procedures listed in Attachment A to assess whether the surveillance procedures satisfied technical speci-fication requirements to support initial criticality and plant heat u Inspection Report 50-410/86-41 described the licensee process of using
Test equipment was calibrated and operated in accordance with procedure.
    -
 
interim surveillance procedures to verify the adequacy of tre surveillance procedure prior to approving the final surveillance procedure in accord-ance with the administrative procedur Discussion The surveillance procedures were found to satisfy technical specification requirement During review of N2-0SP-CSH-M001 and N2-OSP-RHS-M001, the inspector independently parformed a field inspection of several of the as-left valve positions and verified all as-left valve positions in the control roo Findings No violations were identifie .0 QA/QC Interfaces The inspector reviewed three QA Surveillance Reports covering activities associated with the initial fuel loading. The inspector noted that the surveillances included preformulated checklists which detailed critical attributes to be monitored. Surveillance Report SR-86-10837 identified a quality concern relating to the implementation of housekeeping and clean-liness controls per Administrative Procedure AP-P.S. Corrective Action Request (CAR) #86-106 was written by QA requesting formal resolution of the concern by the responsible organization (Operations). The inspector will review this resolution in a future NRC inspectio Findings
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The procedure was technically adequate and appropriate to the circumstances.
 
--
Crew performance was correct and timely.
 
Coordination of test related activities was adequate.
 
--
A preliminary analysis of all data collected was expeditiously
--
performed following completion of the test.
 
--
The test was performed in accordance with all administrative requirements.
 
Discussion
-
N2-SUT-5-0V, Centrol Rod Drive System This startup test includes friction, functional and scram time testing of all control rod drives (CRD's) at a reactor pressure of 0 psig.
 
,
The inspector witnessed performance of section 6.2, Friction Testing, for CRD's 30-07, 30-03 and 26-03. The overall test crew performance was satisfactory. The inspector observed test equipment set up for each rod, initiation of testing for each rod and data reduction following the testing of each rod. All test results were within acceptance criteria limit._.
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'
Findings No violations were identified.
 
3.0 Surveillance Procedure Review Scope The inspector reviewed the surveillance procedures listed in Attachment A to assess whether the surveillance procedures satisfied technical speci-fication requirements to support initial criticality and plant heat up.
 
Inspection Report 50-410/86-41 described the licensee process of using
-
interim surveillance procedures to verify the adequacy of tre surveillance procedure prior to approving the final surveillance procedure in accord-ance with the administrative procedure.
 
Discussion The surveillance procedures were found to satisfy technical specification requirements.
 
During review of N2-0SP-CSH-M001 and N2-OSP-RHS-M001, the inspector independently parformed a field inspection of several of the as-left valve positions and verified all as-left valve positions in the control room.
 
Findings No violations were identified.
 
4.0 QA/QC Interfaces The inspector reviewed three QA Surveillance Reports covering activities associated with the initial fuel loading. The inspector noted that the surveillances included preformulated checklists which detailed critical attributes to be monitored. Surveillance Report SR-86-10837 identified a quality concern relating to the implementation of housekeeping and clean-liness controls per Administrative Procedure AP-P.S.
 
Corrective Action Request (CAR) #86-106 was written by QA requesting formal resolution of the concern by the responsible organization (Operations). The inspector will review this resolution in a future NRC inspection.
 
Findings
,.
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No unacceptable conditions were identifie .0 Independent Measurements and Verifications The inspector made independent measurements of control rod drive piston i differential pressures from photographs of oscilloscope traces made during
No unacceptable conditions were identified.
; continuous insert friction testing as part of N2-SUT-5-0 In addition the inspector independently verified as-left valve positions and proper fuel bundle orientation and location as discussed in paragraphs 3.0 and 2.1 respectfully.
 
5.0 Independent Measurements and Verifications The inspector made independent measurements of control rod drive piston differential pressures from photographs of oscilloscope traces made during i
continuous insert friction testing as part of N2-SUT-5-0V.
 
In addition
;
the inspector independently verified as-left valve positions and proper fuel bundle orientation and location as discussed in paragraphs 3.0 and 2.1 respectfully.
 
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Findings No unacceptable conditions were identified.
 
I 6.0 Plant Tours and Meetings The inspector made several tours of various areas of the facility to observe work in progress, housekeeping, cleanliness controls and startup testing activities.
 
In addition, the inspector randomly attended the l
licensee's morning Startup Plan of the Day meeting during which the current
'
status of testing activities and any holds or delays are discussed. Other items such as remaining preoperational testing, surveillance, and outage activities are also discussed. No unacceptable conditions were observed.
 
7.0 Exit Interview A management meeting was held at the conclusion of the inspection on November 21, 1986, to discuss the inspection scope, findings and observa-tions.as detailed in this report (see Paragraph I for attendees).
 
No written information was provided to the licensee at any time during this inspection. The licensee did not indicate that any proprietary informa-tion was contained within the scope of this inspection.


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ATTACHMENT A Surveillance Procedure Reviewed N2-OSP-CSH M001 HPCS Discharge Piping Fill and Valve Line Up Verifi-cation and Check Valve Operability Test, Revision 0, Final Surveillance procedure performed on October 29, 1986.
 
N2-OSP-CSH-0001 HPCS Valve Operability Test, Revision 0, Final Surveillance Procedure performed September 18, 1986.
 
N2-0SP-CSL-R0001 LPCS Pressure Isolation Valve Leakage Test, Interim Surveillance procedure performed August 16, 1986.
 
N2-0SP-CSL-CS001 LPCS Cold Shutdown Valve Operability Test, Interim Surveillance Procedure performed July 7, 1986.
 
N2-OSP EGS-M102 D/G Operability Test Olvision III, with Strip Chart Recorder Hookups, Revision 0, Final Surveillance performed November 8, 1986.
 
N2-0SP-EGS-R004 Operating Cycle Diesel Generator Simulated LOOP with ECCS Division I and II, Interim Surveillance procedure performed August 14, 1986.
 
N2-OSP-RHS-M001 RHR Discharge Piping Fill (LPCI) and Valve Lineup Verifi-cation and Check Valve Operability, Revision 0, Final Surveillance performed October 24, 1986.
 
N2-0SP-RDS-M001 Scram Discharge Volume Vent and Drain Valve Position Verification, Interim Surveillance performed September 6, 1986.
 
N2-OSP-RDS-Q001 Scram Discharge Volume Vent and Orain Valve Operability Test, Interim Surveillance performed August 6, 1986.


Findings No unacceptable conditions were identifie I 6.0 Plant Tours and Meetings The inspector made several tours of various areas of the facility to observe work in progress, housekeeping, cleanliness controls and startup testing activitie In addition, the inspector randomly attended the l licensee's morning Startup Plan of the Day meeting during which the current '
N2-ISP-CMS-R101 Channel Calibration of the Remote Shutdown Monitoring Suppression Pool Water Level, Revision 0, dated October 25, 1986, Interim Surveillance procedure performed June 8, 1986.
status of testing activities and any holds or delays are discussed. Other items such as remaining preoperational testing, surveillance, and outage activities are also discussed. No unacceptable conditions were observe .0 Exit Interview A management meeting was held at the conclusion of the inspection on November 21, 1986, to discuss the inspection scope, findings and observa-tions.as detailed in this report (see Paragraph I for attendees). No written information was provided to the licensee at any time during this inspection. The licensee did not indicate that any proprietary informa-tion was contained within the scope of this inspectio .
_ . .


..
N2-ISP-CSH-R106 Operating Cycle Calibration of HPCS actuation on Drywell Pressure High Instrument Channels 2ISC*PIS1667C,G,L and R, Interim Surveillance procedure performed June 18, 1986.
 
N2-ISP-NMS-R202 Fixed Neutron Flux Response, Revision 0, dated July 28, 1986 Interim Surveillance procedure performed May 5, 1986.
 
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ATTACHMENT A Surveillance Procedure Reviewed N2-OSP-CSH M001 HPCS Discharge Piping Fill and Valve Line Up Verifi-cation and Check Valve Operability Test, Revision 0, Final Surveillance procedure performed on October 29, 198 N2-OSP-CSH-0001 HPCS Valve Operability Test, Revision 0, Final Surveillance Procedure performed September 18, 198 N2-0SP-CSL-R0001 LPCS Pressure Isolation Valve Leakage Test, Interim Surveillance procedure performed August 16, 198 N2-0SP-CSL-CS001 LPCS Cold Shutdown Valve Operability Test, Interim Surveillance Procedure performed July 7, 198 N2-OSP EGS-M102 D/G Operability Test Olvision III, with Strip Chart Recorder Hookups, Revision 0, Final Surveillance performed November 8, 198 N2-0SP-EGS-R004 Operating Cycle Diesel Generator Simulated LOOP with ECCS Division I and II, Interim Surveillance procedure performed August 14, 198 N2-OSP-RHS-M001 RHR Discharge Piping Fill (LPCI) and Valve Lineup Verifi-cation and Check Valve Operability, Revision 0, Final Surveillance performed October 24, 198 N2-0SP-RDS-M001 Scram Discharge Volume Vent and Drain Valve Position Verification, Interim Surveillance performed September 6, 198 N2-OSP-RDS-Q001 Scram Discharge Volume Vent and Orain Valve Operability Test, Interim Surveillance performed August 6, 198 N2-ISP-CMS-R101 Channel Calibration of the Remote Shutdown Monitoring Suppression Pool Water Level, Revision 0, dated October 25, 1986, Interim Surveillance procedure performed June 8, 198 N2-ISP-CSH-R106 Operating Cycle Calibration of HPCS actuation on Drywell Pressure High Instrument Channels 2ISC*PIS1667C,G,L and R, Interim Surveillance procedure performed June 18, 198 N2-ISP-NMS-R202 Fixed Neutron Flux Response, Revision 0, dated July 28, 1986 Interim Surveillance procedure performed May 5, 198 . .
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. 2 N2-ISP-NMS-R106 APRM Flow Biased Thermal Power Upscale Trip RC Time Constant Verification, Revision 0, dated August 16, 1986, Interim surveillance procedure performed June 18, 198 ,
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N2-ISP-NMS-R106 APRM Flow Biased Thermal Power Upscale Trip RC Time Constant Verification, Revision 0, dated August 16, 1986, Interim surveillance procedure performed June 18, 1986.
 
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Latest revision as of 20:56, 5 December 2024

Insp Rept 50-410/86-64 on 861117-21.No Violations Noted. Major Areas Inspected:Power Ascension Test Results Evaluation,Power Ascension Test Witnessing,Surveillance Procedure Review & Qa/Qc Interfaces
ML20212A357
Person / Time
Site: Nine Mile Point Constellation icon.png
Issue date: 12/12/1986
From: Marilyn Evans, Florek D
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20212A306 List:
References
50-410-86-64, NUDOCS 8612220384
Download: ML20212A357 (9)
v • d • e


Text

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U.S. flVCLEAR REGULATORY COMMISSION

REGION I

Report No. 50-410/86-64 Docket No. 50-410 License No. NPF-54 Licensee: Niagara Mohawk Power Corporation 300 Erie Boulevard, West Syracuse, New York 13202 Facility Name: Nine Mile Point Nuclear Station, Unit 2 Inspection At:

Scriba, New York Inspection Conducted: November 17 - 21, 1986 Inspector:

D an/

/2 - / 2 - Bf

,

M. Evant,, Repctor'

eer date Approved by:

Dri//ot m'

/2 - /2 - 84 fu D. FloreY Cpief, f

date

/

Test Programh Sec Wn, 08, DRS Inspection Summary:

Inspection on November 17 - 21, 1986 (Report No. 50-410/86-64).

Areas Inspected: Routine unannounced inspection by one region based inspector of power ascension test results evaluation, power ascension test witnessing, surveillance procedure review, QA/QC interfaces, independent measurements and verifications, and plant tours and meetings.

Results: No violations were identified.

Note:

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

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-

1.0 Persons Contacted Niagara Mohawk Power Corporation

  • M. Boyle, Nuclear Compliance and Verification
  • J. Conway, Power Ascension Manager
  • W. Hansen, Manager, Nuclear Quality Assurance (QA), Operations
  • M. Jones, Superintendent Operations J. McKenzie, Quality Surveillance
  • T. Newman, Supervisor, Operations Surveillance
  • J. Perry, Vice President, QA
  • A. Pinter, Site Licensing Engineer
  • P. Wilde, QA Surveillance Supervisor Other NRC Personnel
  • W. Cook, Senior Resident Inspector
  • W. Schmidt, Resident Inspector

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

2.0 Power Ascension Test Program References

Regulatory Guide 1.68, Revision 2, August 1978 " Initial Test Program for Water 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, 1986.

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

NMP-2 Safety Evaluation Report.

Overall Power Ascension Test Program Initial Fuel Loading was completed on November 15, 1986. At the time of this inspection open vessel testing was proceeding smoothly with startup tests N2-SUT-05-0V, CRD and N2-SUT-13-0V, Process Computer remaining to be

+

completed.

_. _

__

.

  • 2.1 Power Ascension Test Results Evaluation Scope The power ascension test results discussed below were reviewed to verify that:

--

The test was performed in accordance with a current, approved procedure.

--

Test changes were approved in accordance with administrative procedures.

--

Test changes are annotated in the procedure and completed, if appropriate.

The basic objectives of the test were met.

--

--

Test deficiencies are documented, as required.

--

Test deficiencies were resolved, accepted by management and retests completed, if required.

System or process changes necessitated by test deficiencies have

--

been properly documented and reviewed.

--

Test. deficiencies which constitute reportable occurrences have been properly reported.

--

Required test data has been obtained and is within tolerances.

~

--

Individual test steps and data sheets have been properly initialed and dated.

--

An engineering evaluation of the test data has been performed.

Test results are evaluated against established acceptance

--

criteria.

--

Review and acceptance of test results has been documented.

--

Tests results have been reviewed by Quality Assurance or other Independent Organization.

Test results have been approved by appropriate management.

--

Discussion

-

N2-SUT-1-0V, Chemical and Radiochemical

--

-

.

--

- _

._-

.

-

The inspector reviewed the preliminary test results package and noted that a test exception had been written for a level 1 acceptance criteria concerning condensate demineralizer effluent dissolved 0 concentration. The 0 concentration was out of

2 specification high at 8300 ppb (requirement of 20-200 ppb). The licensee's resolution was to accept as is because the 20-200 ppb requirement applies at operating conditions only.

Five additional test exceptions not related to acceptance criteria were identified and properly dispositioned.

-

N2-SUT-2-0V, Radiation Measurements The inspector reviewed the preliminary test results package and verified that all acceptance criteria were satisfied.

-

N2-SUT-3-0V, Fuel Loading The inspector independently evaluated the preliminary test results including the 1/M plots maintained during the loading and the partial core shutdown margin test.

In addition, the inspector reviewed portions of video tapes of the core verifi-cation conducted by the licensee following loading of the 362nd fuel bundle and following loading of the last fuel bundle (764th). The licensee verified proper fuel bundle orientation and location as documented in N2-RPSTP-5, Core Verification.

Fuel loading began on November 2, 1986 and the last bundle was loaded on November 15, 1986. All acceptance criteria were satisfied. One test exception was generated for having the "C" SRM bypassed while loading fuel bundles into the "C" quadrant.

This is discussed further in the Senior Resident Inspector's inspection report (50-410/86-56).

-

N2-RPSTP-1, Shutdown Margin Test Due to the occurrence of several spurious neutron monitoring system scram signals, the licensee performed this test to demonstrate sufficient full core shutdown margin. Once demon-strated, the RPS shorting links were reinstalled, therefore restoring RPS coincident logic and eliminating the spurious scram signals.

The inspector reviewed the results of this test and verified that sufficient shutdown margin was demonstrated.

>

Findings No unacceptable conditions were identifie,

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2.2 Power Ascension Test Witnessing-Scope The inspector witnessed portions of the power ascension test discussed below. The performance of this test was witnessed to verify that:

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The current, approved revision of the test procedure was available and in use by all participants.

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The minimum crew requirements, as defined in the approved procedure and technical specifications, were being met.

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Required prerequisites and initial conditions were established.

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Test equipment was calibrated and operated in accordance with procedure.

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The procedure was technically adequate and appropriate to the circumstances.

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Crew performance was correct and timely.

Coordination of test related activities was adequate.

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A preliminary analysis of all data collected was expeditiously

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performed following completion of the test.

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The test was performed in accordance with all administrative requirements.

Discussion

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N2-SUT-5-0V, Centrol Rod Drive System This startup test includes friction, functional and scram time testing of all control rod drives (CRD's) at a reactor pressure of 0 psig.

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The inspector witnessed performance of section 6.2, Friction Testing, for CRD's 30-07, 30-03 and 26-03. The overall test crew performance was satisfactory. The inspector observed test equipment set up for each rod, initiation of testing for each rod and data reduction following the testing of each rod. All test results were within acceptance criteria limit._.

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Findings No violations were identified.

3.0 Surveillance Procedure Review Scope The inspector reviewed the surveillance procedures listed in Attachment A to assess whether the surveillance procedures satisfied technical speci-fication requirements to support initial criticality and plant heat up.

Inspection Report 50-410/86-41 described the licensee process of using

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interim surveillance procedures to verify the adequacy of tre surveillance procedure prior to approving the final surveillance procedure in accord-ance with the administrative procedure.

Discussion The surveillance procedures were found to satisfy technical specification requirements.

During review of N2-0SP-CSH-M001 and N2-OSP-RHS-M001, the inspector independently parformed a field inspection of several of the as-left valve positions and verified all as-left valve positions in the control room.

Findings No violations were identified.

4.0 QA/QC Interfaces The inspector reviewed three QA Surveillance Reports covering activities associated with the initial fuel loading. The inspector noted that the surveillances included preformulated checklists which detailed critical attributes to be monitored. Surveillance Report SR-86-10837 identified a quality concern relating to the implementation of housekeeping and clean-liness controls per Administrative Procedure AP-P.S.

Corrective Action Request (CAR) #86-106 was written by QA requesting formal resolution of the concern by the responsible organization (Operations). The inspector will review this resolution in a future NRC inspection.

Findings

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No unacceptable conditions were identified.

5.0 Independent Measurements and Verifications The inspector made independent measurements of control rod drive piston differential pressures from photographs of oscilloscope traces made during i

continuous insert friction testing as part of N2-SUT-5-0V.

In addition

the inspector independently verified as-left valve positions and proper fuel bundle orientation and location as discussed in paragraphs 3.0 and 2.1 respectfully.

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Findings No unacceptable conditions were identified.

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

In addition, the inspector randomly attended the l

licensee's morning Startup Plan of the Day meeting during which the current

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status of testing activities and any holds or delays are discussed. Other items such as remaining preoperational testing, surveillance, and outage activities are also discussed. No unacceptable conditions were observed.

7.0 Exit Interview A management meeting was held at the conclusion of the inspection on November 21, 1986, to discuss the inspection scope, findings and observa-tions.as detailed in this report (see Paragraph I for attendees).

No written information was provided to the licensee at any time during this inspection. The licensee did not indicate that any proprietary informa-tion was contained within the scope of this inspection.

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ATTACHMENT A Surveillance Procedure Reviewed N2-OSP-CSH M001 HPCS Discharge Piping Fill and Valve Line Up Verifi-cation and Check Valve Operability Test, Revision 0, Final Surveillance procedure performed on October 29, 1986.

N2-OSP-CSH-0001 HPCS Valve Operability Test, Revision 0, Final Surveillance Procedure performed September 18, 1986.

N2-0SP-CSL-R0001 LPCS Pressure Isolation Valve Leakage Test, Interim Surveillance procedure performed August 16, 1986.

N2-0SP-CSL-CS001 LPCS Cold Shutdown Valve Operability Test, Interim Surveillance Procedure performed July 7, 1986.

N2-OSP EGS-M102 D/G Operability Test Olvision III, with Strip Chart Recorder Hookups, Revision 0, Final Surveillance performed November 8, 1986.

N2-0SP-EGS-R004 Operating Cycle Diesel Generator Simulated LOOP with ECCS Division I and II, Interim Surveillance procedure performed August 14, 1986.

N2-OSP-RHS-M001 RHR Discharge Piping Fill (LPCI) and Valve Lineup Verifi-cation and Check Valve Operability, Revision 0, Final Surveillance performed October 24, 1986.

N2-0SP-RDS-M001 Scram Discharge Volume Vent and Drain Valve Position Verification, Interim Surveillance performed September 6, 1986.

N2-OSP-RDS-Q001 Scram Discharge Volume Vent and Orain Valve Operability Test, Interim Surveillance performed August 6, 1986.

N2-ISP-CMS-R101 Channel Calibration of the Remote Shutdown Monitoring Suppression Pool Water Level, Revision 0, dated October 25, 1986, Interim Surveillance procedure performed June 8, 1986.

N2-ISP-CSH-R106 Operating Cycle Calibration of HPCS actuation on Drywell Pressure High Instrument Channels 2ISC*PIS1667C,G,L and R, Interim Surveillance procedure performed June 18, 1986.

N2-ISP-NMS-R202 Fixed Neutron Flux Response, Revision 0, dated July 28, 1986 Interim Surveillance procedure performed May 5, 1986.

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N2-ISP-NMS-R106 APRM Flow Biased Thermal Power Upscale Trip RC Time Constant Verification, Revision 0, dated August 16, 1986, Interim surveillance procedure performed June 18, 1986.

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