IR 05000336/1986014
| ML20205G868 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 07/25/1986 |
| From: | Finkel A, Jerrica Johnson NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20205G847 | List: |
| References | |
| 50-336-86-14, NUDOCS 8608190644 | |
| Download: ML20205G868 (8) | |
Text
rn-
.,
.
l
.
!
i U.S. NUCLEAR REGULATORY COMMISSION l
REGION I
l Report No.
50-336/86-14 Docket No.
50-336 l
License No. DPR-65 Licensee: Northeast Nuclear Energy Company P.O. Box 270 Hartford, Connecticut 06141-0270 Facility Name: Millstone Unit 2 Inspection At: Waterford, Connecticut Inspection Conducted: July 7M 1, 1986 Inspectors:
.M MM
A.Finkel/Leid'[eictorInsdftor
' date Approved by:
eM S/
7ASYl J.
hnson,' Chief,pperationalPrograms
/
d6te tion, Operations Branch, DRS Inspection Summary: Routine, unannounced inspection on July 7-11, 1986 l
[ Inspection Report 50-336/86-14)
Areas Inspected: Surveillance testing and procedures, calibration control, quality assurance / quality control interfaces and licensee actions on previous inspection findings.
t Results: No violations were identified.
l l
l ko 4 960soe O [I$00yK 05000336
.
!
l PGR
,
t-
L.
,
_
=
-___
n
.
.
.
.
DETAILS 1.0 Persons Contacted Northeast Nuclear Energy Company
- D. Kross, Instrumentation and Control Supervisor
- W. Romberg, Station Superintendent
- S. Scace, Millstone Unit 2 Superintendent U.S. Nuclear Regulatory Commission
- G. Grant, Resident Inspector T. Rebelowski, Senior Resident Inspector The inspector also held discussions with managers, supervisors and other licensee employees during the course of inspection, including operators, technical and-administrative personnel.
- Denotes those present at the exit meeting on July 11, 1986.
2.0 Followup on Previous Inspection Findings (Closed) IE Information Notice No. 86-53 - Improper installation of heat shrinkable tubing.
Problems involving improper installation of heat shrinkable tubing manufactured by Raychem have been identified at a number of plants.
The licensee uses the Raychem Application Guide for WCSF-N titled,
"In-Line Splice Application Guide," Revision 2, dated August 1983, plus a training program that has been developed by the Raychem Company for the installation of their splice material.
During the use of the Raychem WCSF-N sleeve material, the installation personnel consider the following criteria:
Material size
--
Cable cleaning and preparation
--
Minimum length of WCSF-N material not less than 21" per side
--
s To assure that the licensee was in compliance with their procedures the inspector selected the following Plant Design Change Requests (PDCR!s) for verification with plant procedures, Plant Design Change Request (PDCR) 2-87-85,. October 22, 1985,
--
Replace Core Exit Thermocouple Terminal Blocks Inside Containment, PDCR 2-88-85, October 24, 1985, Terminal Blocks Inside Containment
--
Used for Instrumentation Circuits, and PDCR 2-20-85, February 26, 1985, Terminal Blocks Inside Containment
--
Used for Instrumentation Circuits
.
.
,
.
I.
-
In each of the above referenced PDCRs splices were made per AMP Instruc-tion / Maintenance Sheet No. IS 1535 August 23, 1971 and Raychem In-Line Splice Application Guide. The QC inspection plans were complete with no outstanding items identified.
The inspector's review of sample splices made using the Raychem WCSF-N material and In-Line Splice Application Guide verified that the installations were in accordance with the plant guidance and quality control inspection sheets.
The sample splices that the inspector reviewed were performed using the same methods and techni-ques that were verified in NRC Inspection Reports 50-336/77-34, 78-02, 78-14, and 78-07.
This item is closed.
3.0 Administrative and Operating Surveillance Testing Program
,
l l
The inspector ascertained that the licensee has developed and implemented
'
a Quality Assurance (QA) program for the administration and conduct of surveillance testing during the operational phase of the Millstone Unit 2 plant. This program was reviewed against regulatory requirements and commitments in the Technical Specifications and 10 CFR 50.55a(g).
Attachment I lists surveillance test and calibration procedures for l
safety-r' elated equipment and systems that the inspector selected for i
review for inclusion of the following items:
Master Schedule for surveillance testing and calibration of Technical
--
,
Specification requirements
!
Frequency for test / calibration inspection
--
.-
Responsible organization identified
--
.
Surveillance Test status
--
!
Master Schedule updated to reflect TS or license revisions
--
Quality Assurance responsibilities
--
l Final review and acceptance of work performed
--
The inspector's review of the procedures listed in Attachment I verified l
that the above criteria were included in the licensee's program.
3.1 Administrative Control Procedure (ACP) ACP-QA-1.02, Revision 17 Administrative Control Procedures (ACP's) have been written which define the licensee's methods and responsibilities for complying with their Technical Specifications (TS), ANSI-N18-7, ANSI N45.2.12, and Regulatory Guide 1.8, Revision 1.
!
- -
- -
.
.
.
The Instrumentation and Control (I&C) Supervisor reports to the Unit 2 Superintendent. He serves as a member of the PORC and is aesponsible for establishing standards and frequency of calibrations, and assures that instrumentation and related testing equipment are properly used, inspected and maintained. He also assures that the Technical Specification requirements for equipment listed on the Master Schedule are complied with on the scheduled dates listed.
The Maintenance Supervisor has the same generic responsibilities as those of the I&C Supervisor for his area of responsibility which consists of gages, tool blocks, and torque wrenches. Gages and Fluke Instruments used by maintenance are calibrated and controlled by the I&C section.
During this inspection the inspector witnessed the surveillance testing of RPS Matrix Logic Trip Relays, the RPS Bistable Trip Test and the calibration of two Fluke (multimeter) Instruments and 3 torque wrenches.
In each of the above cases the items tested were within the specification requirements.
No violations were identified.
4.0 Seismic Monitoring Instrumentation System The inspector reviewed the seismic monitoring instrumentation data and hardware installation for compliance with the criteria of 10 CFR 100, Appendix A, VI, (a), (3) " Required Seismic Instrumentation," Regulatory Guide 1.12 " Nuclear Power Plant Instrumentation for Earthquakes" and the facility Technical Specifications (TS), section 3.3.3.3.
- 4.1 Seismic Instrumentation and Control Procedures The seismic monitoring instrumentation surveillance requirements are listed in Technical Specification Table 3.3-7.
A review of the data associated with functional testing of the instrumentation and sensors was selected by the inspector on a random basis and is listed below:
Monthly testing channel checks were performed on the following
--
equipment Time History Accelerographs located at the Containment Slab and Structure, Auxiliary Building, Intake Structure
'
and Free Field locations.
,
Eighteen month calibration of the Time History Accelerographs,
--
Peak Accelerographs, Seismic Trigger and Response Spectrum Recorder data.
In reviewing the test documentation associated with the I&C test procedures and program, the inspector verified that the equipment met the requirements of the monthly channel check and I
- -
- - - - - - -
-
- - - - - -
- - - - - - -
--
-
- -
-
-
. - - - - -
- -
-
- -
.
.
-
the 18 month calibration test procedure and was in compliance with the requirements of the Technical Specifications. The test documentation reviewed by the inspector is listed in Attachment 1 of this report.
4.2 Response Spectrum Recorder (RSR)
The 18 month data for the RSR located at the Containment Base Slab is sent to Engdahl Enterprises for review.
In their letter of March 7,1986 the consultant approved the test data and verified the equipment to be operable and within the design specification for this site.
4.3 Seismic Equipment Installation In verifying the seismic instrumentation installation and locations as listed in the Technical Specification, page 3/4 3-33, the inspector selected the Control Room Seismic Panel, Containment, Auxiliary Building and Intake Structure Time History Accelerographs and the Containment Base Slab Seismic Trigger and Response Spectrum Recorder. A review of equipment history records and procedure results (listed in Attachment 1) indicated that the equipment was within the TS requirements.
The Unit 2 Containment Base Slab tri-axial accelercmeter channels with triggers were clean when observed by the inspector. The inspector verified that the installation was in accordance with the as-built drawings and that the maintenance
.
records were updated as required by procedures.
No inadequacies were identified during the inspection and review.
5.0 Quality Assurance Program for Surveillance Testing and Calibration The inspector ascertained that the' licensee has developed and implemented program control and evaluation techniques that comply with the surveillance testing, calibration and inspection criteria required by section 4 of their Technical Specification.
5.1 Audits The inspector reviewed the licensee's audit program to verify implementation of the program elements required by 10 CFR 50, Appendix B, Criterion XVIII and section 17.2 of the FSAR.
In addition several audit reports containing deficiencies and/or comments were reviewed for content, timeliness of answers, qualifications of the individuals performing audits and the audit schedules.
5.1.1 Audits Reports l
The following audit reports were reviewed by the inspector to verify that the licensee was in compliance with Millstone Unit 2 Technical Specification (TS) Section 6.5.3.7.
Audit
-
-
.
-
-
-
.
.
.
.
A22001, which was performed during the period of March 17-31, 1986, reviewed seven (7) disciplines, of which Instrumentation and Controls (I&C) was one of the seven disciplines audited.
The audit findings were identified to the licensee's management for corrective action.
The audit reports are still open, but the response to the findings have been issued and were in the review cycle during this inspection period.
The overall response to the audit findings by the licensee was timely and generally the responses were technically sound.
Where a disagreement existed between the audit personnel and a supervisor's response, additional time was taken to address the disagreement and issue satisfactory corrective action.
Two other audit reports were reviewed by the inspector with the same results as referenced above. The audit reports listed below were in the final review cycle for closing during this inspection period. The delay in closing these reports was due to an audit finding in the method of handling the generic Nonconformance Report (NCR) forms.
Since the audit report included Units 1, ; and 3, the closing of the NCR concern required all three plants to correct the finding and approve the corrective action. Answers were being prepared during this inspection period.
Audit Report A60435, Starting July 18, 1985, to verify
--
implementation of TS Sections 6.5.3.7.c, Requirements of Actions to Correct Deficiencies Audit Report A60459, Starting March 17, 1986, to verify
--
that plant system / components fabrications are controlled using the applicable QA program requirements.
No violations were identified.
.
6.0 Exit Meeting The inspector met with licensee management representatives (see Section 1.0 for attendees) at an exit meeting on July 11, 1986. The inspector summarized the scope and findings of the inspection at that time.
At no time during the inspection was written material provided to the licensee by the inspector.
,
t
-
r
,
.
.
ATTACHMENT 1 General Procedures Quality Assurance Audits, ACP-QA-9.01, Revision 12, January 24, 1986
--
Quality Assurance Surveillance Program, ACP-QA-9.07, Revision 0
--
February 1,1985 Control and Calibration of Measuring and Test Equipment, ACP-QA-9.04
--
Revision 18, April 2, 1986 Unit 2 Surveillance Master Control List, ACP-QA-9.02B, Revision 11,
--
May 27, 1986.
Surveillance Procedures:
Monthly Reactor Protection System High Power Trip Test, 2401F, 6-3-86
--
RPS Bistable Trip Test SP2401G, 6-3-86
--
RPS Matrix Logic and Trip Path Relay Test, SP24010, 6-1-86
--
Thermal Margin / Low Pressure Calculator Test, SP2401J, 6-23-86
--
Functional Test of Auto. Aux. Feedwater Initiation Logic, SP2402M.
--
6-23-86 Quarterly Unit 2 Stack Gaseous Process Radiation Monitor, RM-81328 Calibration,
--
SP2404AF 6-16-86 Unit 2 Radiological Effluent Flow Instrument Functional Test and
--
Calibration, SP2404BB 6-16-86 Seismic Procedures:
Seismic Events System Channel Check, SP2405A, Revision 5, April 9, 1986,
--
Seismic Events System Calibratton, SP2405C, Revision 3, April 4, 1986
--
Spectral Response Seismic Monitor Calibration, SP2405E, Revision 2,
--
December 9, 1982
,
,
.
-
i u
.
.
.
.
.
.
.
.
..
..
.
.
_
_.
- _ -,
.
..
ATTACHMENT 1 CONTINUED
'
Seismic Monthly Test Reports Data:
--
November 21, 1985 Procedure SP24058 February 10, 1986 Procedure SP2405A March 10, 1986 Procedure SP2405A April 8, 1986 Procedure SP2405A May 1986 Procedure SP24058 May 13, 1986 Procedure SP2405A Seismic 18 Month Test Report
--
f February 19, 1986 Procedure SP2405E I
i
!
i f
,
I
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _.. _ _ _ _ _ _ _ _ _ _. _ _ _ _ _ _ _ _ _ _ _. _. _ _ _ _ _ _ _ _ _.. _ _ _ _ _ _ _,
.
..