IR 05000322/1982006
| ML20052B324 | |
| Person / Time | |
|---|---|
| Site: | Shoreham File:Long Island Lighting Company icon.png |
| Issue date: | 03/24/1982 |
| From: | Bettenhausen L, Pullani S NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20052B316 | List: |
| References | |
| 50-322-82-06, 50-322-82-6, NUDOCS 8204300289 | |
| Download: ML20052B324 (7) | |
Text
.
.
,
U.S. NUCLEAR REGULATORY COMMISSION
'
Regfon I Report No. 50-322/82-06 Docket No. 50-322 License No. CPPR-95 Priority
--
Category B
Licensee: Long Island Lighting Company -
175 East Old Country Road Hicksville, New York 11801 I
Facility Name: Shoreham Nuclear Power Station
,
Inspection At: Shoreham, New York Inspection Conducted:
, March 8-12, 1982 Inspectors:
3 23!82
'
S.V.'Pul nir-Reactor Inspector date signed date signed Approyed By:
hp)( Y,Ite+a--
3/M/g2-.
L.H.BettEnh'ausen, Chief, Test Program Section date signed Engineering Inspection Branch Inspection Summary:
Inspection on March 8-12, 1982 (Report No. 50-322/82-06)
Areas Inspected:
Routine, unannounced inspection of preoperational test procedure review, preoperational test witnessing, preoperational test
!
results evaluations, and tours of the facility. The inspection involved 8 inspector hours in office and 40 inspector hours onsite by one region based NRC inspector.
Results: No violations or deviations were identified.
.
82 0 4 30 oM91
e-s - -
-
-
,--e
,
.r
,~~ - - - -
--
,
-
__ _ _ -___ __
.
.
DETAILS
1.
Personnel Contacted Long Island Lighting Company (LILCO)
- W. Judge, Assistant Project Engineer
- J. McCarthy, QA Section Supervisor
- R. Werner, Operational QA Engineer General Electric (GE)
D. Laughman, Test Engineer K. Nicholas, Lead Startup Engineer, NSSS R. Nordman, Test Engineer J. Whittaker, Test Engineer Stone & Webster (S&W)
J. Lee, Work Coordinator
- W. Matejek, Lead Advisory Engineer US Nuclear Regulatory Commission
- J. Higgins, Senior Resident Inspector The inspector also talked with and interviewed other licensee and con-tractor employees during the course of the inspection.
- denotes those present at the exit interview.
2.
Preoperational Test Procedure Review i
The following approved issues of preoperational test procedures were reviewed for compliance with NRC requirements and licensee commitments:
i
--
PT.611.001-1, Revision 1, Preoperational Test Procedure, Reactor l
Protection System.
--
PT.118.001-1, Revision 1, Preoperational Test Procedure, Reactor Building Closed Loop Cooling Water System.
--
PT.122.001-1, Revision 1, Preoperational Test Procedure, Reactor Building Service Water System.
As a result of the above review, the inspector discussed several questions with licensee personnel. These questions were satisfactorily resolved by the detailed explanation presented and further verified by the inspector by review of pertinent records except that two items need further information for their resolution as indicated below. A brief discussion of these questions follows:
.
_ -
_ - _ - - - - _ - _ - - - _
_
~
'
.
.
2.1 PT.611.001-1, Revision 1, Preoperational Test Procedure, Reactor Protection System According to Shoreham Final Safety Analysis Report (FSAR), Chapter 14, Initial Test and Operation, and the Shoreham Startup Manual, Section 2, References, the licensee is committed to Regulatory Guide 1.68, Preoperational and Initial Startup Test Programs for Water-Cooled Reactors, November 1973. Appendix A, Section 3, of the above
Regulatory Guide, requires the Reactor Protection System (RPS) be tested to demonstrate redundancy, coincidence, independence, and safe failure on power loss.
The inspector questioned how the test
,
will comply with the above commitments. The licensee personrel explained that certain sections of the test contain detailed steps
to demonstrate the above commitments. The inspector verified this by detailed review of Sections 8.3, 8.4, and 8.7 of the test pro-
-
cedure and an overall review of the remaining sections.
.
The inspector stated that FSAR Test Abstract 14.1.3.7.35, RPS Pre-operational Test, commits to certain tests for RPS Motor Generator sets. The licensee personnel stated that these tests are included in PT.312.001A-1, Revision 1, and PT.312.0018-1, Revision 1, 120V AC RPS MG Sets Preoperational Tests. The inspector noted that one of the tests for RPS MG sets committed by FSAR Section 14.1.3.7.35,
'
namely the test for measuring the time to come to speed, is not included in the above test procedures. The licensee personne?
stated that they will initiate a test change notice to include this test. This is an Unresolved Item (50-322/82-06-01).
The inspector stated that FSAR Test Abstract 14.1.3.7.35, RPS Pre-operational Test, commits to demonstration of proper functioning of each individual RPS sensor and that the test as described generally satisfies this, except that Subtest 8.5, Reactor Vessel High Pressure
'
.
Trips, and Subtest 8.8, Primary Containment High Pressure Trips, are-
)j performed by simulating the trips from their respective trip cards (electronic modules) rather than from the sensors.
The licensee
~
personnel explained that the circuits from the sensors to the trip cards have been previously verified during the Checkout and Initial Operation (C&IO) phase of the RPS.
The inspector verified this by review of test results CS.611.001-1, Revision 1, RPS Specific C&IO.
The inspector reviewed the acceptance criteria for scram response times in Subtests 8.19 through 8.24 for conformance with their source document, Technical Specification, Preliminary Issue, dated February 1, 1982, Table 3.3.1-2, Reactor Protection System Response
,
i Times'
The inspector noted that Subtest 8.21 Test Data Sheets for
.
Tests 3 and 4, APRM Thermal Trip Response Time Measurements, specify j
the acceptance criterion to be within the range 5.49 to 6.69 seconds,
-whereas TS Table 3.3.1-2 Item 2.b specifies less than or equal to 0.09 seconds (not including simulated thermal power time constant).
l The licensee personnel stated that the acceptance criterion as
!
k
_. __,
_ _, _
, _. _ _ _ _ _ _
_
._ - -.
_,.
.
_ _
__
.
.
!
!
specified on TS Table 3.3.1-2 Item 2.b will be revised to show the correct acceptance criterion (5.49 to 6.69 seconds). This is an Unresolved Item (50-322/82-06-02).
The inspector stated that FSAR Test Abstract 14.1.3.7.35, RPS Pre-operational Test, commits to a " Full Scram Test" to demonstrate proper operation of the entire system. The inspector noted that the test as described in Section 8.25, Reactor Manual Scram Test, calls for data recording for only 4 selected control rods. The inspector questioned whether this implies that the remaining control rods will be hydraulically isolated during this test.
The licensee personnel stated that no control rod is hydraulically isolated; a full scram of all control rods will be verified during this test as committed in the FSAR Test Abstract.
The test is to be performed as a part of PT.106.001, Revision 0, Control Rod Drive System Preoperational i
Test.
The inspector verified this by review of the above test procedure.
The inspector stated that FSAR Test Abstract 14.1.3.7.35, RPS Pre-operational Test, commits to demonstration of proper functioning of all RPS annunciators.
The licensee personnel explained that the annunciators are verified during the C&IO phase using generic procedures CG.000.004-5, Revision 5, Instrument or Control Component Checkout &
Calibration, and CG.000.019-2, Revision 2, Illuminated Window Type Annunciators with specific data sheets for RPS.
The inspector verified this by review of the above generic procedures and random samples from the specific data sheets for RPS.
The inspector stated that FSAR Test Abstract 14.1.3.7.35, RPS Pre-operational Test, commits to verification of end actions for auxiliary actions associated with a trip of the RPS. The licensee personnel
'
explained that this verification is performed as part of praoperational
tests for those systems to which the RPS auxiliary action signals are inputs. The inspector verified this by rev'ew of a random sample preoperational test procedure, PT.106.001 Revision 0, Control
,
Rod Drive System Preoperational Test.
The inspector stated that FSAR Test Abstract 14.1.3.7.35, RPS Pre-operational Test, commits to verification that no scram occurs when I
only one out of the two trip systems are lost. The licensee personnel i
explained that this is included in Subtest 8.3, Scram Pilot Valve
'
Solenoids and Backup Scram Valve Solenoids Verification. The inspector verified this by a detailed review of the above subtest.
2.2 PT.118.001-1, Revision 1, Preoperational Test Procedure, Reactor
Building Closed Loop Cooling Water System I
The inspector reviewed this procedure for compliance with the licensee i
commitments, namely, the requirements of RG 1.68, November 1973, Preoperational and Initial Startup Test Programs for Water Cooled Power Reactors, and the system preoperational test abstract, FSAR i
,-
- - - -,. _. - -. - - _ _.
.
.
- - -
-
-
_- -
_.
--
-
. -..
_
_
-
.
.
Section 14.1.3.7.13, Reactor Building Closed Loop Cooling Water System Preoperational Test. The inspector also reviewed the re-ferenced Startup Test Procedure STP-37, Revision 2, Reactor Building Closed Loop Cooling and Drywell Cooling, to verify that the heat removal capability test for the system is included in STP-7 as stated in PT.118.001-1.
The inspector did not have any questions on these procedures.
2.3 PT.122.001-1, Revision 1, Preoperational Test Procedure, Reactor Building Service Water System
The inspector reviewed this procedure for compliance with the require-ments of RG 1.68, and the system preoperational test abstract, FSAR Section 14.1.3.7.7, Service Water System Preoperational Test. The inspector also reviewed referenced Startup Test Procedure STP-42, Revision 1, Service Water System, to verify that the heat removal capability test for the system is included in STP-42 as stated in FSAR Section 14.1.3.7.7.
The inspector did not have any questions on these procedures.
!
The inspector did not identify any items of violation or deviation.
3.
Preoperational Test Witnessing On March 8,1982, the inspector witnessed portions of Subtest 8.27, IRM Scram Response Time Test, of Preoperational Test PT.611.001-1, Revision 1, Reactor Protection System. The purpose of this subtest was to measure the scram response time for the intermediate range monitors. As a part l
of his observations, the inspector verified that:
--
The test was conducted using the approved and latest revision of the
,
procedure.
l
--
Test equipment was properly calibrated and installed.
--
Test data was collected and recorded in an approved manner.
,
,
--
Test personnel were suitably qualified and knowledgeable of the procedure requirements.
The inspector did not identify any items of violation or deviation.
4.
Preoperational Test Results Evaluation The inspector reviewed results of certain subtests which were part of PT.611.001-1, Revision 1, Preoperational Test, Reactor Protection System, and which were complete as of March 8, 1982. The results reviewed were of the following subtests:
__
-
,
.
--
Subtest 8.2, RPS Relay Energization Verification.
--
Subtest 8.4, Neutron Monitoring System Trips.
Subtest 8.5, Reactor Vessel High Pressure Trips.
--
--
Subtest 8.6, Reactor Vessel Low Water Level Trips.
--
Subtest 8.8, Primary Contair, ment High Pressure Trips.
--
Subtest 8.11, Reactor Manual Scram Trips.
--
Subtest 8.15, Hot Short Tests.
--
Subtest 8.16, Scran Reset Trips.
--
Subtest 8.17, RPS Double Contact Test.
--
Subtest 8.21, APRM Scram Response Time Test.
Subtest 8.26, RPS Input to NS' and RMCS.
--
As part of these test results evaluation, the inspector reviewed the following records on a sampling basis:
--
RPS System Boundary Package C71-B, dated 11/18/80.
--
Con'ditional Subsystem / Component Release to Startup C718-1, dated 7/31/81.
--
Conditional Subsytem/ Component Release to Startup C71B-2, dated 10/28/81.
RPS Master Punch List C71-B, dated 2/10/82.
--
--
RPS Instrument Calibration Re;ords done using procedure CG.000.004-5, Revision 5, Instrument or Control Component Checkout and Calibration.
--
RPS Instrument Loop Check Records done using procedure CG.000.005.004-2, Revision 2, Look Check.
--
RPS Annunciator Checkout Records done using procedure CG.000.019-2, Revision 2, Illuminated Window Type Annunciators.
.
--
Jumpers and Lifted Leads Records for RPS Panel P609, RPS Division 1 and 2 Logic, done in accordance with Administrative Procedure 4.4.2, Revision 10, Jumpers and Lifted Leads, LILCO Startup Manual.
The inspector verified that the test results were being adequately evaluated, test data met acceptance criteria, and the test results were being evaluated by the licensee personnel in accordance with the approved procedures.
The inspector did not identify any items of violation or deviatio.
.
^l
'
5.
Plant Tours The inspector made several tours of_the facility during the course of the inspection. The tours included the reactor building, turbine building and control room. During these tours, the inspector observed and evaluated work in progress, general equipment protection and cleanliness controls, component tagging for safety and jurisdictional purposes, and testing of Reactor Protection System.
No violations or deviations were identified.
6.
Unresolved Items Unresolved items are matters about which more information is required to ascertain whether they are acceptable or whether they are violations or deviations. Unresolved items are discussed in the report above.
7.
Exit Interview The inspector met with licensee management representatives (see Section 1 for attendees) at the conclusion of the inspection on March 12, 1982.
The inspector summarized the scope and findings of the inspection at that time.
.
.