IR 05000322/1989002
| ML20236B956 | |
| Person / Time | |
|---|---|
| Site: | Shoreham File:Long Island Lighting Company icon.png |
| Issue date: | 03/10/1989 |
| From: | Blumberg N, Caphton D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20236B950 | List: |
| References | |
| 50-322-89-02, 50-322-89-2, NUDOCS 8903210391 | |
| Download: ML20236B956 (8) | |
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U.S. NUCLEAR REG'JLATORY COMMISSION
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REGION I
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Report No.
50-322/89-02 Docket No.
50-322 License No. HPF-36
' Licensee:.Long Island Lighting Company 175 East Old Country Road
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Hicksville, New York ~ 11801 Facility Name:
Shoreham Nuclear Power Station Inspection At:
Shoreham, New York Inspection Conducted: January '9-13,1989 Inspector:
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D. L.~ Chpht'on, Senior' Technical Reviewer date
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ii. J. Bluitb(rg, Chief, OpeMtional Program date Section I
Inspection Summary:
houtine Unannounced Inspection on January 9-13, 1989 (Report No. 50-322/89-02)
Areas Inspected:
Routine, unannounced inspection of the licensee's preparations, staf fing, organization and p ogram for conducting the power ascension test program (PATP) for Shoreham including quality assurance for the PATP.
Results: The licenste has updated the PATP as permitted by 10 CFR 50.59 and the Shoreham license.
The inspection found acceotable 10 CFR 50.59 reviews for several Updated Safety Analysis Report (USAR) changes.
However, cne change will reqJire additional information before final acceptability car, t,e determinea.
Plans are in place to increase the staffing of the PATP organization up p issuance by the NRC of a greater than 5% license.
The PATP description in the USAR needs updating regarding the organization and staffing.
No violations or unresolved items were identified.
l NOTE: For acronyms not defined refer to NUREG-0544 " Handbook of Acronyms and Initialisms"
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8903210391 890313 PDR ADOCK 03000322 e
o PDC
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i DETAILS 1.
Per,ons Contacted Long Island Ligh'.ing Company (LILCO)
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- B. Beytin, Systems Engineer
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- L.- Britt, Manager, Nuclear Licensing M. Case, Operations Engineer
- A. Dubison, Licensing Engineer
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- G. Gisonda, Supervisor, Nuclear Licensing l
- R. Grienseich, Operational Compliance Engineer
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- R. McNair, Nuclear Engineer
- R. Pauly, Nuclear Engineer j
- J. Rigert,flanager,' Nuclear Services Division
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- J. Scalice, Assistant Plant Mar,ager
- C. Seaman,. Quality Systems Manager
- S. Skorupski, Assistant Vice President, Operations
- D. Smith, Compliance Engineer:
- W. Steiger, Plant Manager J. Varley, Systems Engineer
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U.S. Nuclear Regulatory Commission F. Crescenzo, Senior Pesident Inspector
- Denotes those present at the exit meeting held on January 13, 1989.
The inspector also c.antacted other licensee personnel in the technical, QA, und operations' staff during the coursa of the inspection.
2. 0 Power Ascension Test Prog.am (PATP) (72400)
2.1 Scope.of Review This inspection reviewed the PATP and changes made to the program,
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the staffing for the PATP, the organization, and procedures for
conducting testing.
Spacific attention was given to two licensee
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letters that made changes to the PATP.
See Attachment A for
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procedures reviewed.
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2.2 Organization and Administration for the PATP l
'l 2.2.1 Discussion l
i The licensee's procedure SP 12.075.01, provides the administrative controls for the PATP.
The procedure also
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describes the organization and responsibilities for j
personnel involved including the personnel interfaces.
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H Procedure SP 12.075.02 provides administrative controls for ensurfng that testing.is completed at each power. plateau.
y and concurrences are obtained before. proceeding to the next
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. testing phase or power plateau.
2.2.2 Findings
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The organization as delineated by SP 12.075.'01 has. changed.
.over time and the description provided in the licensees Updated Safety Analysis Report (USAR), Chapter 14 does not describe the existing organization..The. inspector-discussed with licensee management the need to update the PATP description in the USAR Chapter'14. A licensee
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representative-stated that this work ~would be done'and submitted.
Some evidence of.this work effort was observed by the inspector prior to leaving the site. A licensee representative also stated that both procedures SP i
12.075.01 and SP 12.075.02 were being revised to reflect ongoing changes being made.
The licensee's PATP organization staffing at the timeof
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.the inspection had a number of vacancies. The PATP organization is programmed to have 25 people; however, at the time of the inspection there were only seven people
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assigned.. The-licensee's intent is to have all positions
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filled within six weeks of the time the " greater than five
. percent license" is issued by NRC.
Contracts were in place
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-for bringing onboard the additional PATP personnel to rea.ch I
the full staffing level.
Until the organization is
adequately staffed, the licensee's representative stated
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that any PATP testing would be limited. The inspector had no further questions at this time regarding the organization and' administration for the PATP.
2.3 Changes to the PATP-2.3.1-Discussion i
The licensee submitted two letters, dated November 18, 1988, and December 9, 1988, to the NRC describing changes made to the initial test program as described in the
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Shoreham USAR.
This inspection reviewed the acceptability
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of these changes.
The changes were made under tne provisions of 10 CFR 50.59(b) and License condition 2.C.(4) of NPF-36.
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L 2.3.2 Findings L
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a.
Le_tte r : November 18, 1988 L
L The licensee's letter dated November 18, 1988, stated that full closure testing of MSIVs (main steam i
isolation valves) at power was deleted and the justification for full stroke testing at cold shutdown j
was submitted to the NRC as part of the SNPS Pump and Valve Inservice Testing Program (IST), Document No.
L 80A2903, Revision 4.
The inspector reviewed the
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referenced IST cold shutdown justification provided in the subject IST relief request.
The licensee's cold shutdown justification stated that closing these valves..."may be" a large contributing factor in observed seat degradation. Additional information to support this contention or other bases is needed in order to complete the evaluation. The licensee's representative stated that the additional information
would be provided.
This item is left open pending the licensee providing acceptrble additional justification (0 pen Item 322/89-02-01).
b.
.Lette r :
December 9, 1988 The licensee's letter dated December 9, 1988, provided eight changes to the initial test program described in Chapter 14 of the SNPS USAR.
The changes which are listed in Attachment B were submitted in accordance with license NPF-36 condition 2.c(4), 10 CFR 50.71 (e), and 50.59. The ifcensee's 50.59 reviews were
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inspected and all eight changes were found to be acceptable.
Regarding one change, item No. 8 in Attachment B to this report, the licensee's representative stated that based upon NRC Bulletin No.
88-07, Power Oscillations in Boiling Water Reactors (BWRs) including supplement 1, consideration is being
given to not performing TC-4 testing since it is planned not to operate in this region.
Pending the licensee's final disposition of this matter, the inspector had no further questions at this time.
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3.0 Quality Control (QC) Interfaces with the Power Ascension Test Program
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(PATP)
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The inspector interviewed the Quality Control Division Manager regarding the intended QC scope and coverage of the PATP. Work was in progress to complete the 1989 QC surveillance schedule.
The manager stated that the schedule was being coordinated with the audit schedule regarding the timing for surveillance and would be issued after this task is completed. QC performs approximately 25 surveillance per month and uses expertise from other groups to assist in performing surveillance. The QCD manager stated that they have plans to do one backshift surveillance per QC person per month.
The inspector reviewed two completed surveillance,89-001, Second Shift Criticality Surveillance performed on 1/6/89 and 89-002, First Shift Criticality Surveillance performed during t
1/4-5/89 and found them to be acceptable.
4.0 Tours of the Facility The inspector toured the reactor building, including the remote shutdown room, and the control room.
The inspector noted that the housekeeping and overall plant conditions were acceptable.
5.0 Management Meetings Licensee management was informed of the scope and purpose of the inspection at an entrance meeting conducted on January 9, 1989. The findings of the inspection were periodically discussed with licensee representatives during the course of the inspection.
The findings of the inspection were presented at an exit meeting (reference to paragraph 1 for attendees) conducted on January 13, 1989.
The licensee stated that one reference document provided for inspection was considered to be proprietary information by a contractor. The licensee indicated that no other proprietary information was contained in the scope of the
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inspection.
At no time during this inspection was written material concerning inspection findings provided to the licensee by the inspector.
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h Attachment A i
Reference Documents I
Regulator Guide'1.68, Initial Test Programs for Water Cooled Reactor Plants Shoreham Safety Analysis Report, USAR SP 12.075.01 Revision 16, Administration of Startup Testing-SP 12.075.02, Revision 0, Master Ste.rtup Activities List
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Attachment B Listing or Changes To The Initial Test Program
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Reference:
Licensee's letter dated December 9, 1988-Item No.
Subject of Change Reference Change Made Items Reviewed
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1.
STP No. 8, Control USAR Sections Deleted Test-Licensee's 50.59 Rod Saguence 14.1.4.5.27, Control Rod and GE FDDR E> c h a t,ge 14.1.4.8.50, Sequence Field Deviation and Table Exhange Disposition 14.1,1-1 Request) No.
KS1-2459 2.
STP No. 12, APRM USAR Section Deleted Licensee's 50.59 i
Calibration 14.1.4.8.7 certain and GE FDDR No.
specified KSI-2459 R
data under-Item 3, i
namely:
electrical power, steam flow, control i
valve position
and APRM l
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response.
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STP No. 27, USAR Section Provides Licensee's 50.59 j
Turbine 14.1.4.8.24 improved and GE FDDR No.
Generator definition KS1-1283 Load Reject of Level 1 acceptance
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criterion
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for the recircula-tion system pump and
motor time i
constant j
for the two pumps drive flow i
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Item No.
Subject of Change Reference Change Made Items Reviewed 4.
STP No. 28, Shut-USAR Section To Perform Licensee's 50.59 down from Outside 14.1.4.8.25.1, the testing and GE FDDR No.
the Main Control RG 1.68.2 at a power KS1-2459
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Room level of 10 to 25%.
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STP No. 29, USAR Jection Revise test-Licensee's 50.59 Recirculation 14.1.4.8.26 ing and and GE FDDR KS Flow Control acceptance 1-2459RO System criteria relating to automatic load following which will not be used at Shoreham l
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STP No. 30, USAR Section Revised the Licensee's 50.59, l
Recirculation 14.1.4.8.27 test method GE FDDR KS1-System for tripping 2459 and FDDR
.j the recir-KS1-1283 culation system pumps j
and clarifies the level 1
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coastdown j
acceptance
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criteria.
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STP No. 70, USAR Section Provided Licensees 50.59 Reactor Water 14.1.4.8.33 additional and GE FDDR Cleanup System information KS1-2459
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by adding j
two notes to I
the level 2 acceptance criteria.
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SP 12.075.01, USAR Figure Redefines Licensee's 50.59
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Administration 14.1.4-1, Test and GE FDDR of Startup Power Flow Condition KS1-2459 Testing Map and NRC No. 4 Bulletin (TC-4) on 88-07 the power including flow map Supplement 1 to avoid a power oscillation event.
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