IR 05000320/1978013
| ML19220B217 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 04/05/1978 |
| From: | Davis A, Haverkamp D, Nicholas H NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19220B213 | List: |
| References | |
| 50-320-78-13, NUDOCS 7904250517 | |
| Download: ML19220B217 (10) | |
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U.S. NUCLEAR REGULATORY COMMISSION -
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0FFICE OF INSPECTION AND ENFORCEMENT
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Region I Report No. 50-320/78-13 Docket No. 50-320 B-2 Category License No. OPR-73 Priority
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Licensee:
Petrooolitan Edison Comoany P
O. Box 542 Readino, Pennsylvania 19603 Three Mile Island Nuclear Station, Unit 2 Facility Name:
Inspection at: Middletown, Pennsylvania In:,pection conducted: March 23-25,1978
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Inspectors:
D. (.)iavet Reactor Inspector
'date signed 4/1/ k)ampk t/r/w H. H. Nicholes, Reactor Inspector
/date signed date si ned i
Approved by:
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A. B. Davis, Cnier, K05] Lor r WJeCts date' signed Section No.1, Reactor Uperations and Nuclear Support Branch Insoection Summary:
23-25, 1978 (Recort No. 50-320/78-13)
Inspection on MarchRoutine, announced inspection of licensee's action on previous Areas insoected:
inspection findings; preoperational test results evaluation and test results verification; license conditions for Mode 2 Operation; and facility tour.
The inspection invalved 44 inspector hours onsite by two NRC inspectors.
Results: No items of nonccmpliance vaw identified.
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l Region I Form 12
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(Rev. April 77)
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DETAILS 1.
Persons Contacted Metropolitan Edison Comcany
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- Mr. M. Beers, Shift Supervisor Mr. J. Brumer, I&C Supervisor Mr. J. Seelinger, Unit Superintendent - Technical Support General Public Utilities Mr. C. Gatto, Lead Mechanical Engineer Mr. I. Porter, Lead Engineer
- Mr. R. Toole, Test Superintendent
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- denotes those present at the exit interview on March 25, 1978.
2.
Licensee Action on Previous Inspection Findings (Closed) Inspector Followup Items (320/77-42-02 and 320/77-42-03):
Rerun TP 600/14 and TP 600/29.
TP 600/14 was completely rerun and applicable portions of TP 600/29 were rerun during the most recent heatup, as required by the controlling procedure TP 710/2.
The inspector's findings concerning these tests are described in Para-
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graph 4.
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(Closed) Unresolved Item (320/78-08-02):
Administrative procedures for review / approval of radicanalytical procedures. The inspector reviewed the licensee's Generation Procedure GP 1404, Rev. O covering this area and determined that tt provided for the review, approval and maintenance of the radioanalytical procedures. The inspector noted that the responsibility for these functions was assigned to the Radiological Environmental Monitoring Program (REMP) Director, whose position has not been clearly defined in the Met Ed admini-strative structure by procedure or by the ETS. The licensee stated that this definition would be included in a revision to GP 1404 prior to the next routine NRC inspection of the environ-mental programs.
The inspector stated that with the inclusion of the above definition, he had no further questions in this area at this time.
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Precoerational Test Results Verification _
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The inspector reviewed the following tests.
SP 2, Fil'ter Efficiency Tests (MTX 124.7, 136.8, 138.6,
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170.7. 2.5, 33.7 and 77.5)
TP 173/2, Auxiliary' Building Ventilation Functional Test
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(MTX 2.4)
TP 177/2, Fuel Handling Building Ventilation Functional Test
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(MTX 77.4)
TP 202/3, Makeup and Purification System Functional Test
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(MTX 99.6)
TP 231/3, Radwaste Disposal ' Gas) Functional Test (MTX 124.6)
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TP 232/1, Radwaste Disposal (Solid) Functional Test (MTX
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127.6)
TP 350/1, Computer Hardware Verification (MTX 23.1 and 22.1)
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TP 350/10, Computer Inputs Verification (MTX 23.3 and 22.3)
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TP 360/1 A, Radiation Monitoring System Test - Atmospheric
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Monitors (MTX 123.2)
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TP 360/1B, Radiation Monitoring Systcm Test - Liquid Monitors
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(MTX123.3)
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TP 360/1C, Radiation Monitoring System Test - Area Monitors
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(MTX 123.4)
SP 365/2, Loose Parts Monitor Baseline Data Acquisition
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(MTX 95.3)
TP 370/1, Heat Tracing Functional Test (MTX 83.4)
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The test results were reviewed to verify the following items.
Test summaries and evaluations had been performed by the cognizant engineers, and test results had been compared with
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established acceptance criteria Approval of the test results by those personnel charged with responsibility for review and acceptance had been documented,
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and if the offisite 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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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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The test results had received final approval, except as noted below.
TP 360/1A and TP 360/lB have been partially approved as ac-The inspector determined that
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ceptable for entering Mode 2.
the outstanding test exceptions / deficiencies were acceptable for Mode 2 operation and had no further questions concerning
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thess tests.
TF 370/1 has been partially approved, with the exception of evaporator heat tracing. The inspector noted that TP 230/3,
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RC Waste Evaporator Functional Te-t, has been deleted as a license condition for Mode 2 operation. The licensee will complete TP 370/1 in conjunction-with evaporator preoperational testing.
The ir.spector had no further questions concerning this test.
Findings were acceptable.
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4.
Preoperational Test Results Evaluation The inspector evaluated the following tests.
TP 120/5, Spent Fuel Handling Bridge Functional Test (MTX
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78.6)
TP 120/6, Main Fuel Handling Bridge Functional Test 'MTX 78.7)
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TP 120/7, Auxiliary Fuel. Handling Bridge Functional Test (MTX 78.8)
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TP 120/8, Fuel Transfer System and Miscellaneous Functional Tests (MTX 78.9)
TP 200/11, Reactor Coolant Pump Flow Test - Hot, with Core
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(MTX 146.10)
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TP 200/12, Reactor Coolant Flow Coastdown Test - Ho^., with Core (MTX 147.6)
TP 273/3, Emergency Feedwater Pumps Functional Test (MTX
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59.7)
TP 330/3A, Post Core load CRDM Functional Test (MTX 38.5)
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TP 330/5, CRD Trip Test (MTX 38.7)
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TP 600/13, Pressurizer Operational and Spray Flow Test
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(MTX 147.12)
TP 600/14, Pipe and Component Hanger Hot Deflection and
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I.spection Test (MTX 147.15)
TP 600/29, RCS Thermal Expansion Functional Test (MTX 147.16)
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Testing (MTX 147.38)g Procedure for, Post Fuel Load SP 710/2, Controllin
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The test results were evaluated to verify the following items.
Test changes had been approved in accordance witt admini-
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strative procedures, properly entered into the procedure, accomplished if actions were necesrary, ar.d did not change the basic objectives of the test
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Test deficiencies had been resolved, accepted by appropriate management, retest conducted if required, and any system or process changes necessitated have been properly documented and reviewed
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Test summaries and evaluations had been performed by the cognizant 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), test deficiencies noted receive appropriate review and evaluation, and individ-ual test steps and data sheets have been properly initialed and dated
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Quality Assurance inspection records have been completed to
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document the adequacy of the test package contents, to indicate independent review of test records and data package contents,
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and an independent audit was performed during test performance as required by administrative procedures Approval of the test results by those personnel charged with
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responsibility for review and acceptance has been documented, and if the offsite review committee has audited the test package, that their comr.ents are included,and corrective
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action has been taken if required.
I The inspector used one or more of the following acceptance criteria for the above items.
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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, except as noted below.
TP 200/11, TP 200/12, TP 330/5 and SP 710/2 have been partially approved as acceptable for entering Mode 2 using three operablu
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Reactor Coolant Pumps. These tests are scheduled to be rerun prior to entering Mode 2 with four RCPS.
The final approved tests will be reviewed during a subsequent inspection.
(320/
78-13-01)
TP 120/5, TP 120/7 and 120/8 have been partially approved as
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acceptable for initial fuel loading, with a few outstanding exceptions / deficiencies. The tests procedures were turned over to Met. Ed. for completion prior to the refueling equip-ment operation, as documented in GPU letter TMI-II-6712 dated February 14, 1978. The inspector noted that these TP's have been deleted as license conditions for Mode 2 operation and had no further questions concerning these tests.
TP 600/29 has been partially approved as acceptable for Mode
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2 operation with one outstanding deficiency, which is required to be resolved prior to entering Mode 1.
The inspector had no further questions concerning this test..
5.
Review of Facility Goeratino License DPR-73 Conditions for hade 2 Operation Incomolete Work Lists a.
During this inspection the Incomplete Work Lists for the following systems were reviewed.
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Control Building Area Ventilation Control Building Ventilation
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Control Rod Drive System
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Fuel Handling Building Ventilation
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Heat Tracing
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Hydrogen System
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Incore Monitoring System
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Instrument Air System Nuclear Instrumentation
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Radiation Monitoring System
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Radwaste Disposal - Gas, Solid, Liquid Reactor Protection System
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Spent Fuel Cooling System
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The work lists were reviewed to verify that there were no significant incomplete items which would affect the capability of the systers to perform their intended function.
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were acceptable.
b.
Radiological Environmental Monitorina Proaram Administrative
. Controls Administrative procedures for review / approval of radio-analytical procedures have beer, provided in Generation Pro-cedure GP 1404, Rev. O.
Additional infurmation regarding this item is discussed in Paragraph 2.
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Post Accident Shutdown Monitorina Instrumentation Reduadant non-nuclear instrumentation indicators for post accident shutdown monitoring of pressurizer and steam gener-ator levels were installed under completed FCR 2418.2.
The inspector reviewed the FCR documentation package and observed the installed instruments.
Finoings were acceptable.
d.
Make-up Tank Hydrocen Charoino Line Modification and
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Make-up Sysnem Operation Double isoli. tion solenoid valves were provided in the make-up tank hydrocen supply line by completed ECM #5-5340.
Operating procedures 2104-1.2 and 2101-1.1 were changed to require appropria'e Make-up Tank charging levels and pressures.
Pro-cedures 2104-1.2 and 2202-i.3 have been changed such that the Make-up System configuration is in accordance with Met Ed letter Gal 0404, dated March 14, 1978.
Findings were accept--
able regarding these license conditions.
e.
Fire Prctcchion System Imorovements During a facility tour on March 24, 1978, the inspector verified completion of the following license conditions re-lated to improving the capability of fire protection systems:
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Fire detectors have been properly relocated in the Control Room.
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In the Control Room Kitchan area a grease filter has been installed over the range, an additional Class B portable extinguisher has been provided, and the wooden cabinet was removed.
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Smoking prohibition signs have been posted in designated fire areas.
Findings were acceptable.
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6.
Facility Tour The inspector toured accessible plant areas at various times during March 23-25, 1978. The tours were conducted to observe general cleanliness and housekeeping conditions and potential
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r,afety and fire hazards. The inspector noted that extensive claanup activities were in progress during the inspection, and housekeeping conditions in the Reactor f ailding had improved since the last inspection.
The inspe: or stated that plant areas would be reinspected for adequate cleanliness control and fire pro'ection prior to entering Mode 1.
(320/78-13-02)
7.
Exit Intervie3L The inspeucor met with licensee representatives (denoted in Para-graph 1) on Maren 25, 1978 to discuss the findings of the inspec-tion.
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