IR 05000320/1977023
| ML19220C305 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 06/14/1977 |
| From: | Davis A, Fasano A, Kellogg R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19220C303 | List: |
| References | |
| 50-320-77-23, NUDOCS 7904300159 | |
| Download: ML19220C305 (6) | |
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT Region I Report No.
77-23 Docket No.
50-320 License No.
CPPR-66 Priority
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Category B
Licensee:
Metropolitan Edison Company Box 542 Reading, Pennsylvania 19603 Facility Name:
Three Mile Island Unit 2
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Inspection at:
Middletown, Pennsylvania Inspection conducted.
May 27 and 31 - June 3,1977
/ /f [7 Inspectors:
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'tof/ Inspector dgtesi@ed
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eactor Inspector date /si gn'ed
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R. S. Mar 6 ki, Reactor Inspector date signed Approved by:
M/f/77 A. B. Davis, Chief, Reactor Projects Section (ate tigned No. 1, RO&NS Branch Inspection Summary:
Inspection on May 27 and 31 - June 3,1977 (Report No. 50-289/77-14)
Areas Insoected: Routine, announced inspection to witness the conduct of testing pressurizer code safety valve; witnessing the cold hydro-static test and follow-up on previous unresolved items.
The inspection involved 86 inspector hours on site by three NRC inspectors.
Resul ts : No items of noncompliance were found.
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Region I Form 12
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(Rev. April 77)
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7SO4300ISS
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DETAT_LS 1.
Persons Contacted Metrooolitan Edison Comoany Mr. S. Joules, Maintenance Forenan Mr. G. P. Miller, Unit 2 Superintendent Mr. T. O'Connor, Quality Control Inspector Mr. J. Principe, Quality Control Inspector Mr. R. Snow, Maintenance Foreman GPUSC
- Mr. M. Nelson, Technical Engineer Mr. S. Poje, Lead Test Engineer, Mechanical
- Mr. R. Toole, Test Superintendent UE&C Mr. B. A. Bozarth, Phase 2 QC Engineer Mr. W. Japak, State Code Inspector
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Mr. Acheson, Royal Globe Inspector The inspector also talked with and interviewed other licensee representatives and employees including members of the technical engineering and operational staff.
- Denotes those present alorg with the three USNRC inspectors present at the exit interview.
2.
Licensee Action on Previous Inspector Findinas (Closed) Unresolved Item 320/77-16-02: The method tc assure the sample exit tempcrature.
Reference paragraph 9.1.1 of the Nuclear Chemical Addition and Sampling System Operational Test procedure, for clarification of intent.
The test is to verify that the secon-dary ccoler has the capability of maintaining the 0.4 gpm sample of primary fluid at/or belcw 120 F.
In paragraph 9.6.1 of this procedure reference is made to Operating Procedure OP 2104-1.12 Reference TCN-2, 6/2/77.
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3.
Pressurizer Code Safety Relief Valve Bench Tests Reference Work Request No. 340, System - Reactor Coolant, Component -
RC-R-1A and B, Code Safety valves.
The purpose of this work request was to check the pressurizer code safety relief valve setting.
The pressure medium for the test was heated nitrogen.
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The inspector witnessed the conduct of the test for code safe'ty valve RC-R-1B, serial No. BN 4232. The inspector observed the crew performance. The inspector also verified that the prerequisites for temperature profile along the body of the valve were met and that calibrated gages and voltmeters were being used.
The data was recorded for final analysis.
The inspector independently recorded the lift pressure for the ob-served valve under test.
Recordings were made on June 2,1977, between 11:30 a.m. to 2:00 p.m.
The licensee's recorded vcives were within i 2 psi of the values independently recorded. The test was also witnessed by the State Code Inspector.
The personnel perfcrmance and the test results were satisfactory.
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No items of noncompliance or deviations were identified.
4.
Hydrostatic Test Witness (MTX 147.5, Reactor Coolant System Hydro Test)
a.
Introduction
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The test pressure was 3135 psig (+10,~0) for the reactor coolant system and 2500 psig (+10, 0) for the annulus. After completion of the 3135 psig hold, plant pressure was reduced to 2500 (+10,-0) and held until the leak inspection of the welds and mechanical fittings within the test boundary was conducted.
b.
Test Witness The following items were evaluated by direct observation or record review on a sampling basis:
(1) The latest copy of referenced drawings were being utilized and valve positions were being checked as specified in the test procedure.
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(2) An " official gage", " backup gage" and " official annulus gage" of the proper ranges had been designated and cali-brated.
(3) The temperature of the reactor coolant system, reactor vessel head flange and steam generator shell were moni-tored as specified in the test procedure.
(4) The temperature difference across the steam generator tube sheet was monitored and was maintained below the maximum specified in the test procedure.
(5) Temporary instrumentation was installed and calibrated.
(6) Weld location maps were available.
(7) The official test gage was observed and a pressure of 3135 psig (+10, 0) was maintained for greater than 15 minutes.
(8)
Inspections of welds, mechanical fittings, and valve packing glands were conducted in four of the designated areas within the test boundary at the 2500 psig plateau.
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These inspections were conducted in conjunction with the designated QC inspections.
No weld leakage within the referenced areas was found.
Leakage in the area of the control rod drive housings (mechanical) was noted.
Retesting at 2500 psig is planned after repairs are completed.
(9)
Connunications between the field stations and the control room were established.
(10) The Makeup System and the Intermediate Cooling System were sufficiently functional to support the test.
The inspector has no further questions in this area at this time.
c.
Crew Performance The fcilowing items were evaluated by direct observation and record review:
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(1) Test briefings had been held.
Meetings were held prior to shift change.
(2) The minimum crew requirements were met.
(3)
Inspection mirrors were utilized.
(4)
Data collected was reported for final analysis.
(5)
Crew actions observed were satisfactory.
(6)
A dry run was held prior to the test.
The QC inspections held at 1200 psig and 2400 psig also served as " dry runs" for the inspection held at the 2500 psig plateau.
The inspector had no further questions in this area at this time.
d.
Raw Data Review An audit of the as run " official field copy" of the test procedure indicated that:
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(1) The acceptance criteria had been met with the exception of mechanical leakage.
The specific areas were noted on the Deficiency / Exception List included within the pro-cedure.
Retesting at 2500 psig is planned after adjust-ments/ repairs have been completed.
This area will be reviewed during a subsequent inspection.
(2) The code inspectors had not signed the Test Resultt of Section 10.9 (page 38).
This item is open (320/77-23-01).
The inspector had no further questions in this area at this time.
5.
Letdown Isolation Valve, MV-V376 During the dudit of the method utilized to generate the weld maps and inspection areas, it was determined that valve MV-V376 was not ins talled. Further questioning determined that the valve had not been received and a spool piece had been welded in its place.
The valve lineup theets were checked to insure that the affected run of piping was included within the test boundary.
Retesting of the affected run of piping will be conducted at 3135 psig after the valve is installed.
This item is open (320/77-23-02).
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6, Loss of 230 KV Bus 4 with three reactor coolant pumps in operation, On May 29, 1977, The Reactor Coolant Pump RCP-2B, the fourth pump was started.
starting of RCP-2B caused the 230 KV Bus 4 to clear, de-en 2A Auxiliary Transfer.
The cause is being was manually tripped from the Control Panel.
investigated and is believed to be due to the curre The incorrect installation is believed to be due to the This item (320/77-23-3) will be further cation.
use of incorrect drawings.
reviewed during a subsequent inspection.
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7.
E,xit Interview
~-Th-e-inspectari; met with licensee representatives (denoted in para-The inspectors summarized the purpose graph 1) on June 3, 197.7.and scope of the inspection and the findin report.
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