IR 05000320/1977034
| ML19220A539 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 09/29/1977 |
| From: | Coleman W, Davis A, Kellogg P NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19220A531 | List: |
| References | |
| 50-320-77-34, NUDOCS 7904230053 | |
| Download: ML19220A539 (10) | |
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U.S. ItUCLEAR REGULATORY COPfilSSI0ti 0FFICE OF INSPECTION AND EtlFORCEMENT
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Region I Report No.
77-34
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Docket No.
50-320 Category B1 License No.
CPPR-66 Priority
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Licensee:
Metrocolitan Edison Ocmoany P. O. Box 542 Readina, Pennsylvania Facility Name:
Three Mile Island Nuclear Station, Unit 2 Inspection at:
Middletown, Pennsylvania t30feptember2, September 6-9, 1977 Inspection conducted-Auc Inspectors:
-74 7 ?M
CFte sfghed P.c/ -
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Y W. Coleman, Reactor inspector
' teats signed di1/.WA L UM/h7
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T. Stetka, Reactor Inspbctor
/ date signed b-Ob2?/17
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/R. Mar o(', Reactor Inspector date signed 9MJ M
Approved by:
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A. B. Da'vis', Chief, Reactor Projects
' dats signed Section No.1, RO&NS Branch
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Insoection Summary:
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Inspection on Aucust 30-September 2, and September 6-9, 1977 (Recort No. 50-320/77-34)
Areas inspected:
Routine, unannounced inspection of licensee action on previous inspection items; witness of relief valve testing; review of pipe support and restraint systems; thennal expansion of piping systems; preoperational test results verification; and site tour. The inspection involved 68 inspector hours onsite by four NRC inspectors.
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Results:
Of the five areas inspected, no items of noncompliance were identified.
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DETAILS 1.
Persons Contacted Metrocolitan Edison Comoany
- Mr. M. Bezilla PORC Secretary
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Mr. E. Daniels, QC Inspector
- Mr. J. Hilbish, Senior Reactor Engineer Mr. Hoyt, Shift Supervisor Mr. T. Mackey, Engineer II, Nuclear
- Mr. G. Miller, Unit Superintendent
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- Mr. J. Seelinger, Unit Superintendent - Technical Support
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General Public Utilities Service Corocration (GPUSC)
, **Mr. R. Fenti. QA Auditor Mr. C. Gatto, Engineer Mr. R. Lentz, Engineer
- Mr. M. Nelson, Technical Engineer
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Mr. R. Orosz, Engineer Mr. I. Porter, Engineer Mr. J. Roberts, Engineer
- Mr. R. Toole, Test Superintendent
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Mr. J. Ulrich, Engineer Burns and Roe Mr. J. Lucena, Engineer United Enoineers and Constructors, Inc.
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Mr. G. Schmidt, Piping Supervisor
- denotes those present at the exit interview on September 2, 1977.
- denotes those present at the exit interview on September 9, 1977..
2.
Licensee Action on Previous Insoection Findinos (Closed) Unresolved item (320/76-07-04):
SP-2, Filter Efficiency Test. The licensee has revised SP-2 to include a precaution con-cerning the circulation of solvent fumes through the carbon filters.
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(Closed) Unresolved item (320/76-17-04): TP 160/4 Reactor Building Hydrogen Control Functiona' Test.
The liccrsee has revised the procedure to include a minimum fan operation time of fif teen ~
minutes.
(Closed) Unresolved item (320/77-03-05):
Inspection Criteria.
Supplemental Instruction 17. Preparation and Ccmpletion of Check-list for Quality Control Surveillances, contains the guidance for
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the performance of work inspections.
This instruction amplifies the Operational Quality Assurance Plan and General Procedure 4012.
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(Closed) Unresolved item (320/77-04-05):
Frocedural Scope.
The licensee has incorporated the inspector's comments in accordance
Procedure sections 3.8.5.2(a) and (b) were not revised. The inspector discussed this matter with the licensee
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and concurred with the licens et's reason for not changing these
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sections.
(Closed) Unresolved item (320/17-04-07):
Procedure Approval.
ihe Unit No. 2 PORC has reviewed AP-10ll, Revision 12 and PCR 77-486
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and approved the procedure for Unit No. 2 on September 1,1977.
The approval was noted on PCR 77-613 to procedure AP-1011.
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(Closed) Unresolved item (320/77-26-03): Minimum Shift Complement.
Procedure 1009, Station Organization and Chain of Command, will be revised in accordance with PCR Ho.77-616 to address the Minimum Shift Complement requirement.
The loss of Containment Integrity requirement is now covered by the following procedures:
2311-5, Containment Integrity, Revision C;
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2301-M8, Containment Integrity Verificaticn, Revision 1;
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2305-R1, ECCS Contain. ment Emergency Sump Inspection, Revision
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0; and 2303-SA2, RB Hatch Leak Rate and Interlock Test, Revision O.
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The inspector reviewed the procedures to verify proper coverage.
(0 pen) Unresolved item (320/77-26-04): Procedural coverage. The inspector reviewed the following procedures:
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AP 1005.16, Search of Individuals and Vehicles, Entries,
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Protected Area, Revision 0 (August 23,1977);
HP 1630, Reactor Building Entry, Revision 0 (August 29,1977);
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OP 2104-6.1, Fire Protection System, Revision 0 (June 20, 1977);
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OP 2104-5.4, Control Building HVAC, Revision 0 (August 29, 1977);
OP 2107-1.4, Heat Tracing System, Revision 0 (August 1, 1977);
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AL 2204-8A Series;
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AL 2204-25.1 Series;
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AL 2204-26 Series;
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AL 2204-29 Series;
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AL 2204-25.3 Series;
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AL 2204-301B Series; and
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AL 2204-310 Series.
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The remaining procedures will be reviewed during a subsequent inspection.
(0 pen) Unresolved item (320/77-26-05):
Procedure Review. The
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following procedures have been revised and were reviewed by the inspector:
SP~2302-R9 by PCR No. 2-77-168;
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2202-1.9 by PCR No. 2-77-182;
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2203-1.1 by Revision 1; and
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2204-4.02 and 2204-4.E2 by.PCR No. 2-77-214.
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In addition, the inspector reviewed the item on procedure SP 2301-M9. Af ter discussion with the licensee, the inspector determined that a change to this procedure was unwarranted.
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The remaining procedures will. be reviewed during subsequent inspections.
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(Closed) Unresolved item (320/77-26-06):
Revise Procedure AP-1001.
The licensee has revised section 3.9.3 in accordance with PCR No.77-612 to include additional procedures required by Regulatory Guide 1.33.
(Closed) Unresolved item (320/77-26-07):
Revise Procedure AP-1001 for PORC review.
The licensee has revised section 3.9.5 in accord-ance with PCR No.77-612 to specify the forwarding of procedure changes to PORC for review.
In addition, the licensee has speci-fied the department heads responsible to assure proper periodic reviews are conducted.
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(Closed) Unresolved item (320/77-26-08):
Revise Appendix B to AP-1001. The licensee has revised Appendix B in accordance with PCR No.77-611 to include procedure 2104-5.13.
(Closed) Unresolved item (320/77-26-Of):
Control of Startup Check-lists. The licensee has revised step 3 6.4.1 of the procedure in accordance with PCR No.77-617 to require that a TCN be written for all temporary changes to startup valve checklists.
(Closed) Unresolved item (320/77-26-11):
Revise AP-1022. The licensee has revised AP-1022 in accordance with PCR No.77-614 that added a new step 3.10.6 to the procedure.
This new step specifies how uncalibrated or damaged test equipment will be stored and controlled.
(Closed) Unresolved item (320/77-26-13):
Revise AP-1027. The licensee has revised the Preventative Maintenance Check Sheet in accordance with PCR No.77-617 to include the inspector's coments.
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(Closed) Unresolved item (320/77-26-14):
Superintendent Operating
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Memos. The licensee has written a new administrative procedure,
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1033, Operating Memo's and Standing Orders, Revision 0.
The inspec-tor reviewed this procedure to verify that ANSI N18.7-1972 require-ments were included.
(Closed) Unresolved item (320/77-26-16): Revise AP-1026. The licensee has revised procedure 1026 in accordance with PCR No.77-615 to add a new step 4.3.1.2.6.c that specifically requires writing of a procedure to fill and vent a system if that system is drained during the performance of the corrective maintenance.
(Closed) Unresolved item (320/77-26-17):
Procedural Revisions.
The licensee has revised the applicable procedures as follows:
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2202-2.1 by PCR tio. 2-77-231;
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2202-1.8 by PCR No. 2-77-232;
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2202-2.5 by PCR No. 2-77-230; and
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2202-2., by PCR No. 2-77-162.
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These revisions add precautions in the procedures that addressed steaming to atmosphere with a steam generator tube leak or rupture.
(Closed) Unresolved item (320/77-26-18):
Review AL 2202-319.A6.
The licensee has reviewed and evaluated the response action required and has revised 2204-319A6 as revision 1.
The inspector reviewed the revision and concurred with the licensee's action.
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(Closed) Unr'esolved item (320/77-16-01):
Functional and Sensi-tivity Testing of Chlorine Detectors.
The requirement for a mini-mum sensitivity has been removed from the proposed Technical Specifi-cation.
A functional test of the detectors is contained in the licensee's monthly surveillance procedure.
This test does verify the ability of the system to detect chlorine.
(Closed) Unresolved item (320/77-20-22):
Local Leak Rate Tests.
(a) The acceptance criteria has been revised to reflect a building volume of 2.1 X 106 cubic feet.
(b) Amendment 57 to the FSAR changed Paragraph 6.2.1.4.4.1 to reflect Pa vice 60 psig as the test pressure.
(c) Temporary Change Notice (TCN) 2 to TP 151/1 added a precaution which calls for the recording of the minimum sensitivity of the flowmeters if the reading is at or below the minimum sensitivity.
(d) TP 151/1 has been revised to place a flowmeter at the gas inlet. The inlet and outlet flows can then be
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compared. The change also included two additional test methods to be utilized if the boundary valves were suspected of leaking excess-ively.
(e) TCN2 added a precaution to ensure the seats of the valves are blown dry with air while cycling the valve.
(Closed) Unresolved item (320/77-26-23):
Rotameter Calibration Data. The calibration data for the rotameters in use 4r local leak rate testing is contained in TP 151/1, Reactor Building Isolation Valve Leak Test.
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Main Steam Safety Relief Valves - Witness of Testing 3.
The inspector observed a portion of TP 271/4, Main Steam Functional Test, which involved lifting the 12 Main Steam Safety Relief Valves The (one at a time) to verify set pressure and proper coeration.
test was conducted at 900 pounds steam generator pressure during HFT.
The inspector's observations of the testing are surr.arized below, The inspector noted that the official, approved copy of TP 271/4 was available and in use by test personnel; test changes a.
Additionally, applicable were incorporated in the procedure.
drawings were available at the test station.
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The inspector noted that the number of personnel available for b.
Personnel present during testing included testing was adequate.
the test engineer, vendor technical representative, code inspector, station QC inspector, and several maintenance personnel.
Personnel were also available at the relief valve discharge line outside the turbine building. The personnel at the test location, in the control room, and outside the turbine building were in constant connunication.
The inspector verified that the licensee had signed off all.
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required initial conditions and prerequisites. The inspector also verified, on a sampling basis, that initial test conditions were met.
The inspector noted that the special test equipment (3 Heise
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pressure gauges) were properly installed and in calibration and that the hydraulic lif ting jack was properly installed on s
the valve stem.
The inspector noted that the test was performed as required by
. the procedure and that data required by procedure was recorded.
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The test data recorded was consistent with the inspector's observations.
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The inspector was present for the testing of six of the 12 f.
safety relief valves. During the testing of one valve,.the This valve remained open for an extended period of time.
excessive blowdown caused the reactor coolant temperature to drop 20 F in five minutes, the allowable cooldown rate is 100 F in I hour.
Additionally, the relief valve discharge
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piping was not completely installed at the time of this
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C testing which allowed the' relieving steam to impinge on
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the side of the reactor buildir.g, and during this excessive blowdown, part of the turbine building metal siding was torn away from the building.
The area involved had been roped off and personnel were guarding the area during testing to prevent possible personnel injury.
The inspector noted that licensee action to r eseat the valve during this event was timely and no other damage was evident.
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Of the six valves witnessed, the inspecter noted that three valves failed to meet the acceptance criteria. Subsequent review of the data for all 12 valves showed that eight of the 12 valves failed. to meet acceptance criteria.
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Subsequently, the retest and setpoint adjustment of valves 3A, 3B, and 6A were observed.
Setpoint adjustments were made to the valves that had previously failed to meet the acceptance criteria.
A one hour cooldown period was utilized between tests to allow the valves to return to ambient conditions.
No items of noncompliance were identified.
The completed data package will be reviewed during a subsequent inspection. '
4.
Pipe Supoort and Restraint Systems and Therra. Exoansion a.
P1ce Hangers and Snubbers The inspector reviewed the results of the ongoing program for checking and setting pipe hangers and snubbers in their hot
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condition. The discrepancy list resulting from this inspection was reviewed. The inspector noted no significant problems with pipe hangers; however, fif teen snubbers in various systems were found to be near their limit of travel. An engineering change notice was issued to reset these snubbers, and they will be monitored again at ambient temperat' re.
u The inspector also conducted a sampling inspection of reactor building pipe supports ar.d restraints. This inspection included observing the condition of associated hardware; freedom of travel for snubbers and spring hangers; spring hanger, snubber and constant support hot settings; any evidence of deformation and corrosion; and any cracks on welded surfaces.
No inade-
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quacies were noted during this tour.
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Thermal Exoansi_on Measurements The inspector reviewed the data recorded for TP 600/29 Thernal
- Expansion Functional Test and TP 600/14 Pipe and Component Hanger Hot Deflection and Inspection Test.
A problem report was issued by GPU tartup after the results of TP 600/14 showed five of eight Reactor Coolant Pump Constant supports failed to meet the acceptance criteria.
During review of TP 600/29 data, the inspector noted that the data was to be extrapolated to the position corresponding to the maximum expected system temperature.
The Feedwater maximum temperature is significantly lower than that for the Main Steam system; however, the procedure required extra-polation of both systems to the same temperature.
This item is unresolved pending a change to the procedure TP 600/29.
(320/77-34-01)
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Both procedures require additional data to be taken when the plant returns to ambient temperature.
No items of noncompliance were identified in this area.
5.
Peocerational Test Results Verification Tests TP 235/2 - Auxiliary Building Sump Test (MTX 5.6)
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TP 203/7 - Decay Heat Removal S.F. Test (MTX 47.10)
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Findinos
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The above listed approved ccmpleted tests were available for review.
The cognizant engineering function had evaluated the test results and signified that the system met design requirements; the test results were compared with pre-established acceptance criteria; and the test results were approved.
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No items of noncompliance were identified.
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Plant Tour The inspector toured selected areas of the plant which included the Reactor Building, Control Room, Auxiliary Building, and the Control and Service Building. The purpose of the tour was to verify system completion status and to monitor for housekee? ng and fire hazards.
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The second half of this inspection was commenced with an unannounced plant tour at 6:30 p.m. on September 6,1977.
No inadequacies were identified.
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Unresolved Items Unresolved items are matters about which more information is re-quired in order to ascertain whether they are acceptable items or items of noncompliance.
The unresolved item identified during this inspection is discussed in Paragraph 4.b.
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Exit Interview The inspector met with licensee representatives denoted in Para-
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graph 1 on September 2 and 9,1977.
The scope and findings of the inspection were summarized by the inspector.
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