IR 05000320/1978011
| ML19220A856 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 03/23/1978 |
| From: | Davis A, Haverkamp D, Kellogg P NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19220A848 | List: |
| References | |
| 50-320-78-11, NUDOCS 7904250040 | |
| Download: ML19220A856 (10) | |
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT Region I Report No. 50-370/78-11 Docket No.
50-320 Category B-2 License No.
OPR-73 Priority
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Licensee:
Metrooolitan Edison Comoany P. O. Box 542 Readina. Pennsv1vania 19603 Facility Name:
Three Mile Island Nuclear Station, Unit 2 Inspection at:
Middletown, Pennsylvania Inspection conducted:
February 23-March 1, and March 8-9, 1978 Inspectors:
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3/2.1/7f Reactprfinspector date signed P.J.KellogNgb~-l
_]hz h2 SZ/
D.HaverKamp,Reactorpnspector date signed BY7f
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T. Rebel ki, Rehctor Inspector
/ date signed Approved by:
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A. B. Day 1s, Chief, Reactor Projects
' cate signed Section No. 1, Reactor Operations and Nuclear Support Branch Inspection Summary:
Insoection on February 28 - March 1, and March 8-9,1978 (Recort No. 50-320/78-11)
Areas Inspected:
Routine, unannounced inspection o. licensee's action on previous inspection findings; preoperational test results evaluation and test results verification; license conditions to enter Operational Mode 4; and compliance with Title 10 requirements. The inspection involved 102 inspector hours onsite by three NRC inspectors.
Results:
No items of noncompliance were identified.
Region I Fom 12 7(' ggg
(Rev. April 77)
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79.042500'/0,
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DETAILS 1.
Persons Contacted
Metropolitan Edison Comoany Mr. R. Bensel, I&C Engineer
. Mr. M. Bezillo, PORC Secretary Mr. J. Floyd, Supervisor of Operations Mr. J. Hilbish, Senior-Reactor Engineer Mr. G. Miller, Station Superintendent
- Mr. J. Seelinger, Unit Superintendent - Technical Support General Public Utilities I
Mr. T. Block, Lead Site OA Auditor
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- Mr. C. Gatto, Lead Mechanical Engineer Mr. S. Levin, Project Engineer Mr. M. Nelson, Technical Engineer Mr. I. Porter, lead Engineer
- Mr. R. Toole, Test Superintendent
- denotes those present at the exit interview on March 9,1978.
2.
Licensee Action on Previous Insoection Findinos (Closed) Open Item (320/77-41-09):
Law. Power Physics Procedures /
Initial Criticality Procedure. A review of the approved procedure indicated the items discussed in the referenced report had been included in the procedure.
(Closed) Inspector Followup Item (320/77-42-01): NSRW Pumps Stopped during 600/21. TP 600/21 Integrated Safety Features Ac-tuation Test was reviewed during Inspection 78-07. The deficiency concern-ing the NSRW pumps was cleared by a satisfactory retest on January 16, 1978.
s (Closed) Unresolved Item (320/77-42-04):
Coordination of surveil-lance on RPS during physics testing.
Surveillance Procedure 2302-
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M6-RPS Channel Functional Test has been changed by TCN 2-78-245 to include the reduced setpoints which-will be in effect during physics testing.
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(Closed) Unresolved Item (320/77-42-05):
TP 710/1 Comments.
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review of TP 710/1, Zero Power Physics Tests indicated the comments contained in the referenced report have been incorpe ated into the approved procedure.
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(Closed) Unresolved Item (320/77-42-06):
Review of 800/21, 710/21.
A review of 710/21 and 800/21 was conducted to verify the TPs contained all the required testing, limitations, precautions, and prerequisites.
(Closed) Open Item (320/77-42-07):
Constant doppler coefficient.
The constant doppler coefficient of 2 PCM is a factor to account for doppler change due to-moderator temperature change while hold-ing power constant and is therefore acceptable.
(Closed) Open Item (320/77-42-08):
TP 800/31 Comments.
A review of the approved procedure indicated the comments concerning TS correction factors for hot channel factors had been incorporated into the procedure.
(Closed) Open Item (320/77-42-09): TP 800/32 Comments. A review of the approved procedure indicated the discrepancy concerning the Class IE distribution system had been corrected.
(Closed) Unresolved Item (320/77-47-01): Two different type screws on MUH-275-S. A review by the licensee and the snubber manufacturer indicated both types of screws were acceptable as they provided no
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function in this type of application of the snubber.
(Closed) Unresolved Item (320/77-47-02):
Discoloration on MUH-279-S.
The licensee reviewed this discoloration with the snubber vendor. The results of this review indicated the discoloration wsLid not affect the operation of the snubber.
Additionally, the review indicated there was nothing in the Reactor Building environ-ment that would adversely affect snubber operation.
(Closed) Unresolved Item (320/77-47-03): Different size and miss-ing cotter pins. The missing cotter pins were replaced.
Preven-tion of this item from recurring will be accomplished by the licen-see'sSection XI program and generic reviews by QC personnel during inspections of imcomplete work.
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Bent base clevis on (Closed) Unresolved Item (320/77-47-04):A reinspection of t DHH 294-S.and had freedom of movement.
not bent U-Bolt clearance not (Closed) Unresolved Item (320/77-47-07):The U-Bolt spacing
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i and found to require contact if no gap was indicated on the draw specified.
Nut arrangement on U-Bolts on large bore hangers has no impac the requirement for a gap.
Control Room Panel Number 3.
(Closed) Unresolved Item (320/78-06 01):
ECM 5606 on the control room panel separation has seen ccm Correct problems (Closed) Inspecter Followup Item (320/78-07-05):The valve position i with valve position indication.The deficiency in TP 600/21 was closed were replaced and retested.
by retest and closecut of Problem Report 2568.
Revise TS to (Closed) Inspector Followup Item (320/78-07-06): Technical Specifica provide meaningful response interval.4.8.1.1.2.C.2 has b s
for each ESFAS timer.
Reactor Vessel vibration (Closed) Unresolved Item (320/78-09-01):The inspector rev inspection.
Findings were acceptable.
result summary.
Flow sensors for boron (Closed) Unresolved Item (320/78-06-08):The inspector sensor and observed the readout device in the instrument shop.
mixing.
Fire surveillanca results.
(Closed) Unresolved Item (320/78-07-01):
The inspector reviewed the completed fire surveillance result the remaining TS surveillance itnas.
Completion of feedwater (Closed) Unresolved Item (320/78-D 03): The feed-TP 315/1 was reviewed during this inspection.
water latch circuit had been response tested and was satisfacto latch.
Complete summaries of (Closed) Unresolved Item (320/78-07-04):The inspector reviewed the co RPS and ESFAS. response times. surveillance 2303 R2, 3 t The response times were within TS limits.
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Containment Spray (Closed) Unresolved Item (320/75-0101):The inspector observed the ex-
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System Expansion Loop Restraints.pansion loop restraints i
Preocerational Test Results Verification 3.
The inspector conduc'.?d a review of the following test results:
TP 160/1, Hydrogen Recombiner Test (fiTX 139.5)
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Control Functional Test (MTX TF 30/4, Reactor ?qilding H2
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TP 180/;, Fiie Protect on Functional Test (MTX 75.6)
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TP 200/2, rurveillance and Radiation Specimen Handling
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Test (MTX 147.4)
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TP 203/4, Decay Heat Removal System (MTX 47.9)
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TP 210/12, Nuclear Chemical Addition Functional Test (MTX
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15.6)
i TP 267/4, Nuclear Services Closed Cooling Water System Functional Test (MTX 110.6)
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TP 271/4, Main Steam Functional Test (MTX 98.7)
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TP 276/3, Condensate System Functional Test (MTX 25.7)
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TP 301/2, NI Detector Cabling and Response Test (MTX 108.1)
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TP 301/3D Determination and Setting of Detector Voltages
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(MTX 108.5)
TP 302/2A, Incore Detector Cabling Chec,ks and Computer Input Verification (MTX 89.4)
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TP 302/2C, Incore Detector Post Installation Electrical
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Test (MTX 89.6)
TP 305/lB, RPS Preoperational Calibration (MTX 151.3)
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TP 350/2, Computer Software Verification (MTX 22.2,23.2)
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TP 350/1D, Computer Input Verification (MTX 22.3,23.3)
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TP 365/1, Loose Parts Monitor Functional Test (KTX 95.2)
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TP 401/3, Station Bat,teries Charge and Discharge Test (MTX 214.4)
TP 600/20, Less or Electric Power Test (MTX 51.26)
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The test results were reviewed to verify that:
Test sumaries and evaluations had been perfonned by the cog-
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nizant engineers, and test results had been compared with estab-lished acceptance criteria; and,
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Approval of the test resui. by those personnel charged with responsibility for review and acceptance had been documented, and if the offsite comittee has audited the test package, that their comments are included and corrective action has been taken if required.
The inspectar used one or more of the following acceptar.ce criteria for the above items.
Final Safety Analysis Report
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Test Instruction 18. Test Procedure Documents
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Regulatory Guides
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Inspector Judgement
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Quality Assurance Program
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Findings were acceptable.
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Preoperational Test Re ults Evaluation The inspector conducted an evaluation of the following tests:
TP 160/3, Reactor Building Emergency Cooling Functional
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Test (MTX 135.6)
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TP 315/1, Safety Related Instrument Response Times (MTX 151.6)
TP 600/10 RCS Hot Leakage Test (MTX 147.11)
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TP 600/28, Controlling Procedure for HFT (MTX 147.14)
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SP 204/4, Reactor Building Spray Nozzle Air Test (MTX 141.7)
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TP 150/6, Reactor Building Purge Suppl 3 and Exhaust Functional
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Test (MTX 138.4)
The test results were evalcated to verify that:
Test changes had been approved in accordance with admini-
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strative procedures, properly entered into the procedure, accomplished if actions were necessary, and did not cnange the
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basic objectives of the test;
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Test deficiencies had been resolved, accepted by appropriate
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management, retest conducted if required, and any system or pro:ess changes necessitated have been properly documented and reviewed; Test summaries and evaluations had been performed by the cog-
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nizant engineers, and test results had been compared with established acceptance criteria;
"As-run" copies of the test procedures contain completed data
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sheets (sample), data are recorded where required and are within acceptance tolerances (sample), 'est deficiencies noted receive appropriate review and evaluation, and individual test steps and data sheets have been properly initialed and dated; Quality Assurance inspection records have been ccmpleted to
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document the adequacy of the test package contents, to indicate independent review of test records and data package contents, and an independent audit was performed during test performance as required by adainistrative procedures; and, t
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Approva' of the test results by those personnel charged with l
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responsibility for review and acceptance has been documented, ana if the offsite review committee has audited the test package, that their comments are included and corrective action has been taken if required.
The inspector used one or more of the following acceptance criteria for the above items.
Final Safety Analysis Report
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Proposed Technical Specifications
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Test Instruction 7, GPU Startup Problem Report
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Test Instruction 9. Conduct of Test
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Test Instruction 13, Test Interface Instructions
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Test Instruction 18, Test Procedure Documents
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Regulatory Guides
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Inspector Judgement
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Quality Assurance Program
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Findings were acceptable.
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Test Results Review Part: ally Completed Precoerational Tests TP 370/1, Heat Tracing Functional Test Results, has been completed in areas of Boric Acid Systems and Chemical Addition..The inspector requested a demonstration of alarm features and liceasee demonstrated loss of voltage to various redundant panels as an additional assur-ance of system readiness for Mode 2.
The completed test will be reviewed prior to criticality.
6.
Conditions of DPR-73 During this inspection, a review of the Incomplete Work Lists for the following systems was conducted:
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Core Flood System
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Environmental Barrier System
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Feedwater Latching System
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Internediate Closed Cooling System
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Loose Parts and Vibration Monitoring System
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Makeup and Purification System
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Mechanical Draft Cooling Tower
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Nuclear Services Closed Cooling System
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Penetration Pressurization System
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Reactor Building Air Cooling System
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Reactor Building Emergency Cooling System
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Renctor Building Hydrogen Control System
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Reactor Building Normal Cooling System
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Reactor Building Purge Supply and Exhaust
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Reactor Building Hydrogen Recombiner System
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Reactor Building Spray System
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Reactor Coolant System Non-Nuclear Instrumentation
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Safety Features Actuation System
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This review was conducted to verify that ' items not completed would
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not affect tne capability of the systems to perfora their intended
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design functions.
Findings were acceptable.
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7.
Reportability of Entry into Deoraded Mode
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The inspector discussed with the licensee's staff the following interpretation of the reportability of entry into a deoraded mode.
The purpose of this thirty-day written report is to provide data on equipment failure, including inoperability.
Therefore, a report is required:
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When the failure is detected while performino a test required by the Technical Soecificaticns to demonstrate operability of the equipment.
This is true even if the failure is detected in a mode for which the Technical Specifications do not recuire operability of the equipment.
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When the failure is detected while the facility is operatinp in a mode for which the Technical Specifications do not specifi-cally state that operability of the failed equipment is not required for that mode (so that operability in that mods is required, either directly or by implication).
A thirty-day written report need not be submitted when equipae.it is removed from service, far reasons other than failure, to enter alternate or degraded modes of operation consistent with the pro-visions of a technical specification.
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Exit Interview
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The inspector met with licensee management (denoted in Paragraph 1)
on March 9,1978, to discuss the findings of the inspection.
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