IR 05000220/1989035
| ML17056A604 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 01/29/1990 |
| From: | Anderson C, Cheung L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML17056A603 | List: |
| References | |
| RTR-REGGD-01.097, RTR-REGGD-1.097 50-220-89-35, NUDOCS 9002130115 | |
| Download: ML17056A604 (16) | |
Text
U.S.
NUCLEAR REGULATORY COMMISSION
REGION I
Report No.
50-220/89-35 Docket No.
50-220 License No.
DRP-63 Licensee:
Nia ara Mohawk Power Cor oration 301 Plainfield Road S racuse New York 13212 Facility Name:
Nine Mile Point Unit 1 Inspection At:
Salina Meadows - Cor orate Office Inspection Conducted:
ecember ll - 15 1989 Inspector:
Leon rd Che g, Senior Reactor Engineer, PSS, DRS Approved by:
C.
. Anderson, Chief, Plant Systems Section, EB, DRS date 5.d date Ins ection Summar:
Ins ection on December 11 -
1989 Ins ection Re ort No. 50-220/89-35
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review the licensee's actions on three RG 1.97 and one electrical restart issues identified in the March and August 1989 inspections.
In addition, two open items from a previous RG 1.97 inspection dated November 14 - 18, 1988 were also reviewed.
Results:
No violations were identified.
Two RG 1.97 and two electrical restart items are closed.
One RG 1.97 restart item and one electrical restart item are updated.'wo open items from a previous inspection, 88-34, are close DETAILS 1.0 Persons Contacted 1. 1 Nia ara Mohawk Power Cor oration NMPC J. Benson,,Senior Engineer, Consulting Services F. J.
Constance, Electrical Engineer M. Dooley, Supervisor, Regulatory Compliance D. Kakubowski, RAP Issue ¹18 Task Manager S.
Kim, Associate Senior Engineer
- B. Nowicki, Senior Engineer, Consulting Services S.
W.
Wi lczek, Jr.,
Manager, Nuclear Technology D. Wolniak, Assistant Project Designer, Licensing 1.2 NMPC Contract Personnel J. Schilder, OEI
"Denotes personnel not present at the exit meeting on September 29, 1989.
2.0
~Per oee The purpose of this inspection was to review corrective actions for Regulatory Guide (RG) 1.97 and Electrical restart issues identified in previous inspections 50-220/89-12 and 50-220/89-23 and in an NRC letter to the licensee, dated April 21, 1989'n addition, two unresolved items identified in the first RG 1.97 inspection, 88-34, conducted during the period November 14 - 18, 1988 were also reviewed.
The results of these reviews are discussed in Sections 3.0, 4.0 and 5.0 of this report.
The status of the RG 1.97 restar t items and Electrical restar t items are listed in Appendix A and Appendix B, respectively.
3.0 Followu of RG 1.97 Restart Items Identified in Ins ection 89-12 3.1 Closed Unresolved Item 50-220/89-12-01 pertaining to the cable separation deficiencies for RG 1.97 instruments.
This item was identified duting the March 1989 inspection and was updated in the September 1989 inspection report (50-220/89-25).
Following the March 1989 inspection, the licensee developed and completed a cable separation evaluation for RG 1.97 Category 1 instruments.
The methodology used for this analysis consisted of the following:
1) the development of one line cable routing sketches for each Category 1 instrument loop from color coded cable routing drawings; 2) the development of a list of potential cable routing discrepancies and cable routing matrices; 3) the development of hazards criteria in evaluating the as-built conditions of the cable routing; 4) the preparation of a walkdown checklist data to identify the presence of fire hazards, fire zones, physical separation of redundant cables and components and the documentation of the as-built cable routing walkdown and; 5) the analysis of the walkdown data documented in the cable separation evaluation repor During the September 1989 inspection, the inspector reviewed the licensee's cable routing analysis, walkdown check sheets, cable routing sketches and matrices, and performed a field walkdown of some of the cable routings.
The inspector had concluded that there were no restart concerns for Unit 1 cable separation deficiencies.
The only open portion of this item was the licensee'
completion of the final review and approval of the RG 1.97 cable separation evalua-tion report.
During this inspection, the inspector reviewed the final version of the licensee's document entitled RG 1.97 Cable Separation Evaluation Report for proper review and approval by licensee management.
The inspector found this document acceptable and this item is closed.
3.2 Closed Unresolved Item 89-12-02 pertaining to inadequate isola-tion between the Non-lE computer and the APRM circuit.
Following the March 1989 inspection, the licensee performed a failure modes and effect analysis (FMEA) and conducted a test for the isolation circuit.
.Both the FMEA and the test report were reviewed by the NRC during the September 1989 inspection (see inspection report 50-220/89-25 para-graph 3.7. 1) and were determined to be acceptable.
The inspector considered this item closed.
3.3 0 en Unresolved Item 50-220/89-12-04 pertaining to the review of alternatives to Category
RG 1.97 instruments.
This item had been updated in inspection report 50-220/89-25, which identified 5 corrective actions to be accomplished by the licensee before restart.
They are:
l.
Additional training for the crews that went through the original training and the remaining operators and staff before restart.
The training lesson plan will include all the necessary information to use alternate instruments per the new updated information of the Special Operation Procedure (SOP).
2.'rovide more information for Drywell water level alternate instruments in the SOP.
3.
List the missing Drywell Temperature instrument for the RG 1.97 instrument listed in the SOP.
4.
Add instrument numbers and ranges for alternate and Regulatory Guide instruments listed in the SOP-14.
5.
Add necessary steps regarding when and how to use the alternative instrument During this inspection, the licensee provided the inspector a draft copy of Special Operating Procedure Nl-SOP-14, Revision 1.
This document incorporates corrective actions 2 through 5.
Specifically, additional information for the Drywell prater level alternate instru-ments is included on page 0 and in Attachment B of SOP-14; the missed Drywell Temperature instrument (TI201-36B) is included in the list on page 7; the instrument numbers and ranges of the primary instruments and alternate instruments are included in SOP-14; the necessary steps regarding when and how to use the alternate instruments are addressed on page 1 of SOP,-14.
This item remains open pending licensee's completion of operator training (scheduled on January 12, 1990)
as indicated by item
above, and final licensee approval of Nl-SOP-14, Revision 1.
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¹ 4.1 0 en Unresolved Item 50-220/89-23-04 pertaining to Plant Modification 85-092 for replacing power feeder cables from Battery Boards ll and 12 to Emergency Diesel Generator Control Panels 102 and 103, respectively.
The existing cables with a s,ngle
¹2AWG conductor per pole were to be replaced with cables having two ¹4/0 AWG conductors per pole.
The licensee's calculation which provides the basis for the plant modification had been reviewed during the August, 1989 inspection.
Initially, Plant Modification 85-092 also included the replacement of the 125.V dc cross-tie cables between control panels 102 and 103.
However, the licensee later determined that this replacement was not needed.
4.2 Following the August 1989 inspection, the licensee completed their analysis, EH0-003, to justify not replacing the cross-tie cable.
During this inspection, the inspector reviewed EHO-003 and determined it to be acceptable.
At the time of this inspection, the installation and termination of the cable were completed and the associated drawings were revised to reflect the as-built condition.
The inspector observed the installed condition of the replacement cable and reviewed some of the as-built documents and did not identify any deficiencies.
Pending final SORC approval of this modification which is scheduled for January 24, 1990, this item remains open.
Closed Unresolved Item 50-220/89-23-01.
This item involved the completion of certain corrective actions and verifications which the licensee committed to in their Restart Action Plan in requalify-ing the two battery charging MG sets as safety-related.
The requa-lification had been completed before the August 1989 inspection except for certain administrative documentation and upper management approvals and except for the issuance of a Design Bases Report for the safety-related battery chargers
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During this inspection, the inspector verified the completion of these items by a review of the administrative documentation and approvals and a review of the design bases documentation and report for the battery'chargers.
This item is closed.
4.3 Closed Unresolved Item 50-220/89-23-05
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This item involved
125 Vdc molded case circuit breakers installed in safety related Battery Boards 11 and 12 and Valve Boards 11 and 12.
The licensee was unable to provide any evidence documenting the testing of these circuit breakers to demonstrate their trip characteristics.
The consequences of one of these circuit breakers not operating as required could result in the loss of a dc bus upstream of the breaker.
Subsequent investigation by the licensee disclosed that the 61 molded case circuit breakers in Battery Boards 11 and 12 could be subjected to short circuit currents as high as 15,356 amperes and that the GE types of circuit breakers installed were not.rated to interrupt more than 10,000 amperes.
Many of the breakers were Type TE which have an interrupting rating of only 1,000 amperes.
As a consequence the licensee elected t replace all of these circuit breakers with Gould-Shawmut Type J fuses which have a
125V dc interrupting rating in excess of 25,000 amperes
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The licensee's investigation of the 28 molded case circuit breakers installed in Valve Boards
and 12 revealed that they are GE Types TEF and THEO which have an interrupting rating of 10,000 amperes.
The maximum calculated short circuit currents at Valve Board ll and 12 are 5,631 amperes and 4,096 amperes respectively.
Therefore, the licensee concluded that the circuit breakers in, these boards are adequate and do not require replacement.
In response to the open item issue of testing the circuit breakers, the licensee conducted an evaluation of the reliability of these types of breakers.
This evaluation included communication with another licensee who had tested these types of breakers without any failures either during the tests or during their 17 years of operation.
Two circuit breakers tested by the licensee also successfully met the test acceptance criteria'ased upon their investigation and other factors including plant availability, the licensee has established a schedule for testing the 28 circuit breakers in Valve Boards 11 and 12.
The schedule covers testing of all of the circuit breakers during the time interval beginning in July 1990 and ending during the 1993 outage.
Based upon the licensee's replacement of the inadequate breakers in Battery Boards ll and 12, the favorable results of the reliability evaluation of the circuit breaker, and the licensee's commitment to a testing schedule for the circuit breaker in Valve Boards 11 and 12 in accordance with an established procedure, the inspector concluded that the licensee's corrective actions are adequate'his item is close.0 Followu of RG 1.97-Items Identified in Ins ection No. 88-34 5. 1 Closed Unresolved Item 50-'220/88-34-01 pertaining to lack of channel independency of RG 1.97 reactor pressure instruments.
During the November, 1988 inspection, two deficiencies were identified for the two reactor pressure channels, PT36-31 and PT36-32:
1) both channels are powered by RPS Bus 11, and 12) pressure recorder PR-ID75 interfaces with both PT36-31 and PT36-32 through selector switch ID20A, no isolation device or separation is provided between channels.
Following the inspection, the licensee determined that the electrical drawing (Drawing ¹C-22004-C, Revision ll dated October 28, 1988) that had been reviewed by the NRC inspectors had erroneously shown that power source No.
ACV-S (supplying power to PT36-32)
was powered by RPS Bus ll.
This drawing was subsequently revised (Revision 13, dated September 29, 1989) to correctly show that power source No.
ACV-S is powered by RPS Bus 12.
The actual power supply ar-rangement is:
PT36-31 is powered by RPS Bus ll, PT36-32 is powered by RSP Bus 12.
I As a resolution to the second deficiency, the licensee issued Nodification Package Nl-89-147 dated August 15, 1989 to rewire selector switch ID20A such that the wiring from PT36-31 and PT36-32 is terminated at a separate switch contact block.
This configuration provides adequate separation between redundant channels.
The inspector considered the licensee's corrective actions accept-able.
This item is closed.
5.2 Closed Unresolved Item 50-220/88-34-06 pertaining to inadequate isolation between six Category 1 transmitters and plant computer inputs'he six affected transmitters are:
torus water level LT50-04, -05 and -06; wide range drywell pressure PT201-2-483 and-484; wide range reactor water level LT36-33.
The scope of this unresolved item is enveloped by the scope of unresolved item 50-220/89-12-05, which remains open at-the time of this inspection and the deficiencies have been included in the licensee's document entitled RG 1.97 Isolation Evaluation Report, Revision 0, dated September 1989.
The inspector considered this item closed.
6.0 Exit Interview At the conclusion of the inspection on December 15, 1989, the inspector met with the licensee representatives denoted in Section 1.0.
The inspector summarized the scope and results of the inspection at that time.
At no time during this inspection was written material given to the license '
APPENDIX A ITEM NUMBER STATUS OF RG 1.97 RESTART ITEMS DESCRIPTION STATUS 50-220/89-12-01 Evaluation of RG 1 '7 cable separa-tion deficiencies.
Closed in thi s inspection (89-35)
50-220/89-12-02 Completion of the failure modes and Closed in this effects analysis for the APRM isola-
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inspection (89-35)
tion deficiencies.
50-220/89-12-03 Review of the RG 1.97 instrument cir-Open.
,Scheduled cuit loading and adequacy of installed for completion on fuses.
01/19/90 50-220/89-12-04 Review of alternatives to the Cate-gory
RG 1.97 instruments for which deficiencies exist.
50-220/89-12-05 Evaluation of the RG 1.97 isolation def ici enci es.
50-220/89-12-06 Identification of RG 1.97 instrument power sources and providing instrument power source information at the site in a form useful to the control room operators.
Open.
Updated in this report (89-35).
Scheduled for com-pl eti on by Ol/12/90 Open.
Scheduled for completion on 01/19/90 Open.
Scheduled for completion on 01/19/90 50-220/89-12-07 50-220/89-12-08 Evaluation of the safety significance of the Reactor Pressure Vessel (RPV)
common tap for the fuel zone water level instrument.
Documenting and docketing Nine Mile
RG 1.97 restart activities.
Open.
Scheduled for completion on 01/12/90 Closed in Inspection 50-220/89-25
ITEM NUMBER 50-220/89"23-01 50-220/89-23-02 50-220/89-23-03 APPENDIX B STATUS OF ELECTRICAL RESTART ITEMS DESCRIPTION Battery charging MG set corrective actions.
Replacement of 125 VDC. Station batt-eries and equalization voltage concern.
Replacement of power cable for power cable for power boards 11, 12, 16 and 17.
STATUS Closed in thi s inspection (89-35)
Open.
Scheduled for completion on 02/10/90 Open.
Scheduled for completion on 12/29/89 50-220/89-23-04 Cable replacement of diesel generators Open.
Updated in 102 and'03 control power.
this report (89-35)
50-"20/89-23-05 50-220/89-23-06 DC breaker testing and replacement of breakers by fuses.
Power cable replacement for Electro-matic relief valves.
Closed in thi s inspection (89-35)
Open.
Scheduled for completion on 01/03/90