IR 05000320/1978006
| ML19220B306 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 02/15/1978 |
| From: | Fasano A, Finkel A, Haynes R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19220B291 | List: |
| References | |
| 50-320-78-06, 50-320-78-6, NUDOCS 7904250615 | |
| Download: ML19220B306 (14) | |
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U.S. NUCLEAR REGULATORY CCMMISSION OFFICE OF INSPECTION AND ENFORCEMENT Region I Re ort No.
50-320/78-06 Docket No.
50-320 License No.
CPPR-66 Priority
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Category B
Licensee:
Metropolitan Edison Cercanv P. O. Box 542 Readino, Pennsv1vania 19603 Facility Name:
Three Mile Island Nuclear Station, Unit 2 Inspection at:
Middletown, Pennsylvania Inspection conducted:
January 16-19, 1978 Inspectors: M#
2 /a/7 r'
u A. M. fasano, Reactor Inspector d1te signed fY 2frof7%
A. E. Finkel, Reactor Inspector
'date signed R. W. McGaughy, Chief, Projects Section RC&ES Branch date signed Approved by:
C, 2//a'/7f-a R. C. Haynes ef, Engineering Support cate signed Section No.
RC&ES Branch Inspection Su=ary:
Inspection on January 16-19, 1978 (Recort No. 50-320'78-06),
Areat Inspected:
Routine, unannounced inspection fer review of nonroutine event reports; action on hulletins and circulars; followup on NRC identified items; licensee action on previous inspected findings; and installation of pipe supports. This inspection involved 57 man-hours on site by 2 NRC in-spectors and a supervisor.
Results: No items of noncompliance were identified.
g Region I Form 12 74~.?23
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j (Rev. April 77)
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7004250 (c/O
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DETAILS 1.
Persons Contacted Princical Licensee Employees T. R. Block, QA Auditor
- J. D. Robinson, Piping and Mechanical Engineer R. Toole, Test Superintendent J. E. Wright, Site QA Manager United Engineers and Constructors, Inc.
- J. W. Furlong, Project Engineer i
The inspector also talked with several other of the licensee em-ployees and the constructor.
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- denotes those present at the exit interview.
2.
Plant Tour The inspectors observed work activities in progress, completed work, and plant status in several areas of the plant.
The inspectors examined work items for any obvious de'octs or noncompliance with regilatory requirements and license ccr.
'ons.
Where more detailed inspec; ion of an area was conducted, the inspection scope and find-ings are described in other paragraphs of this report.
No items of noncompliance were identified.
3.
Succorts for Main Steag MS, and Emergency Feedwater, EF, Valves The inspector reviewed Inspection Report IR P-5028 documenting
' satisfactory inspection of hangers supporting valve Nos. EF-Vil A and EF-VilB.
He also reviewed IR P-5027 documenting inspection of operator supports for valve Nos. MS-V-3A and MS-V-38.
As of January 17, 1978, a licensee designated nonconforming condition exists
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regarding one hole drilled in the wrong area resulting in less than full thread engagement of the belt passir.g thrcugh the holt..
This item is scheduled for resolution by the licensee in accordance with his quality assurance program.
The inspector had no further questier.s concerning the above items.
No items of noncompliance were identified.
4.
Safety Related Pipe Succort and Restraint Systems - Mechanical Snubbers and Pice Conconent Supports The supports were reviewed for the folicwing:
Location and installation according to detail drawingt
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Acceptance of welds - visual
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Sliding surfaces
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Material certification
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The following pipe ccmponent supports were inspected:
Succort Desicnation Detail Drawina No.
Remarks NSH-308-S NSH-308-S Double Mechanical Snubber MUM-48-S 4819-4 Multiple Pipe Support wi'~
' bracket MUH-ll3-S 4701-1 Saddle u,
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MUH-130-S 4718-1 Saddle Support RHR-33-5 3319-1 Multiple Pipe Support w/ box support bracket NSH-15-S 161-1 NSH-14
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MUH-217 4942 7 4 ~ ?.'<.'I3
NSH-348-S NSH-348 MUH-72 4843-1 MUH-125-S 4713-1 The followinn discrepancies wera identified during inspection of the above 11:.3 supports.
a.
Bolts and Screws
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loose screws, bolts, and nuts were observed in various loca-tiens on mechanical snubbers and supports MUH-72, MUH-48-S, NSH-14, and NSH-308-S; oversized bolt holes were identified in the plate supports for MUH-48-S and NSH-14; and bolt sizes used to attach supports MUH-125-S and MUH-ll3-5 do not appear to conform to the detail drawings.
This item is unresolved pending corrective action or evalu-able (78 06-01).ation by the licensee showing existing conditions to b.
J_nstallation Variances from Drawinos
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The following supports as installed varied from the detail i
drawing.
The differences were changes in component members or
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size.
MUH-48-S has a 45 strut member vs.90 as shown. Also,
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it was noted that the pipe bracket upper section is spread.
The licensee will determine if this puts a shear stress on the cotter pin.
Item Nos.10 and 1 of support No. NSH-15-S are installed
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differently than shown on their detail drawing No.161-1.
MUH-125-S dimensions at the lower angle iron member of
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the box construction differed from 5 5/8" specified and 6-1/4" in-place. It was noted that the 5" diameter pipe protection shield was damaged.
The above items are considered to be unresolved pending a licensee review of the as installed condition and drawing reviews (320/78-06-02).
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Eelds e.
A visual inspection of welds was made.
The following items were noted.
MUH-130-5 did not have a size of one weld specified on
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the detail drawing.
RRH-33-S has a required all around weld on plate, item 6
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as shown in detail drawing. ThE east side weld has grooves and abrupt ridges 8 valleys.
NSH-348-S has what appears to be satisfac nry welds but
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the locations do not correspond ;o what is shown on the detail drawing.
The above items are considered te tv :irest rec pending licensee review of drawings and tce in-pl...
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(320/78-06-03).
d.
The inspector reviewed scid hists. es
..u material certifica-tions for supports NSH-3CS-T, t au-4S S, MUH-ll3-S, MUH-130-S, RHR -33-S, NSH-15-S, NSH-14,
.. 'UH-217 The documents were certified and reviewed by Qr.
No items of noncompliance were identified.
5.
Items Identified During Site Visit in August 1977 During a site visit on August 1-3, 1977, members of the NRC staff observed several electrical / instrumentation items about which further information was required.
These included:
(a) separatinn of redundant Class IE wiring in control room panel; (b) installation of fire barriers in redundant safety related cabinets; (c) installa-tion of fire stops and seals for walls and floors; (d) installation of cable splices at containment. electrical penetrations; (e) rewiring of instrument racks 455, 467, and 472; (f) installation of fire barrier material for 4.16KV duct and cable tray separation; and, (g) measures provided which assure appropriate boron mixing in reactor coolant for post LOCA long tenn cooling.
The inspector reviewed the status of each of these items and the findings were as follcws:
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a.
Control Room Panel Number 3 Panel number 3 contained redundant wiring, associated with the containment pressure indicator, which was not physically separated. The inspector revicwed Engineering Change Memo (ECM 5606) dated November 21, 1977.
The ECM required the following change:
Separate wires, in panel 3, from recorder BS-PR-4388 to
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terminal block T63 by six (6) inches (minimum) from wires from recorder BS-PR-1412 to terminal block T57.
The inspector examined the rework in progress, and this item remains open pending completion of ECM 5606.
The inspector also examined the wiring separation in cabinet 21 and the two redundant diesel generator control cabinets in the control room.
He determined that they were in compliance with the separation requirements of Burns and Roe Specifi-cation 2555-70.
b.
Bottom Barriers and Seals for Redundant Safety Related Cabinets Within the main control room there were no bottom barriers and seals internally between the redundant reactor protection
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system channel cabinets. The same concern was noted between the redundant diesel generator control cabinets.
The inspector reviewed Engineering Deviation Report (EDR 4439)
dated January 17, 1978, and General Construction Procedure 7-2 dated December 6,1977.
EDR 4439 required bottom barriers and seals to be installed betveen these redundant safety system cabinets.
This work is in progress and is considered to be unresolved pending review of the completed work and review of QC records by an NRC inspector.
(78-06-04)
c.
Fire Stoos and Seals for Walls and Floors
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Fire stops and seats had not been installed in safety related wall and/or floor openings for cables and/or conduit in the areas listed below.
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The inspector reviewed Engineering Deviation Report (EDR 4439)
dated Januacy 17, 1978, General Construction Procedure 7-2 dated December 6,1977, and form titled, " Fire Wall Breaching Notification."
The inspector examined the fire barriers and seals in the following areas:
main control room
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diesel generator rooms
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diesel generator fuel oil storage tank area
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battery rooms
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compartments for battery charges and static inverters
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In all of the above areas work was in progress, but no areas were complete and accepted by the licensee.
This item is considered to be unresolved pending review of the completed work and review of QC records by an NRC inspector (78-06-05).
d.
Electrical Penetrations and Cable Solices
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(1) Cables leaving cable tray number 3105 and entering the bottom of electrical penetration number 534 were not supported.
The inspector reviewed Engineering Change Memo (ECM 5484)
dated September 27, 1977.
The ECM required the following change:
Install support for cable drop-outs from tray numbers
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3105 and 3106 to penetration R-534 Box.
'This work was in progress during this inspection.
(2) The safety related penetrations are equipped with box enclosures and the licensee is in the process of deter-mining if there penetrations had been qualified with these enclosures.
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The licensee is splicing selected circuits as defined in Field Change Request (FCR) No. 2453.2 and PCN 2453.
The wiring splices are " AMP, IND Nuclear Pre-Insulated Environ-mentally Sealed Splices." The AMP splices were qualified to LOCA requirements by the Franklin Institute and occu-mented in test reports TPR-575-98 and TPR-575-99 dated February 1974.
The inspector reviewed the FCRs.
The qualification test reports TPR-575-98 and 99 were not at the site, but the licensee stated that engineering had reviewed and approved the reports.
Items (1) and (2) above are considered to be unresolved pending inspection of completed work and review of QC records by an NRC inspector (78-06-06).
e.
Instrumentation Rack Rewirino Reactor Protection and Safety Feature Actuation System The reactor protection and safety features actuation system channel wiring was not physically separated in instrument racks 455, 467, and 472.
The inspector reviewed Engineering Change Memo (ECM-5098),
Revision 1, dated September 6,1977, and Quality Control Inspection Report, dated January 15, 1978 (no number identi-fied on QCIR).
These documents address the rewiring racks and
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the inspection report that verified the work.
The inspector visually examined the rewiring in racks 455, 467, and 472.
No items of noncompliance were identified.
f.
Cable Screadino Room (1) Additional protection was added for a 4.16 KV bus duct passing through a portion of the cable spreading room.
The 4.16 KY bus duct will have a new 3-hour fire rating room built to house it where it goes through the spread-ing room. The new room, which will be a Seismic I installa-tion, is defined in Field Change Request (FCR 2453.1)
dated December 2, 1977, and drawings 4300, Revision 16; 4414, Revision 7; 4443, Revision 23; 4446, Sheet 1, Revision 27; 4448, Revision 11; and 4450, Revision 13.
The inspector witnessed the in-progress installation of the seismic wall supports.
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(2) Redundant cable trays No. 3248 and 4228 crossed each other horizontally with less than the minimum vertical physical separation (3 feet) between them and no barrier had been installed.
The inspector witnessed the installaticn of the fire barrier material on safety related cable tray 3248 as required by B&R Specification 2555-70 Section 165 (Fire Barriers and Fire Stops) and Section 162 (Physical Separ-ation and Identification Requirements for Safety Related Electrical Systems and Equipment).
The inspector noted that fire barrier material is being
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installed on safety related cable trays throughout the plant.
Licensee was in progress. QC acceptance checks of the installatien
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Items (1) and (2) above are considered to be unresolved pending inspection of the completed work and review of the QC records by an NRC inspector (78-06-07).
Flow Sensors Used to Assure Long Term Boron Mixino Following g.
a LOCA i
A flow sensor probe located in the piping run from the reactor vessel hot leg to the suction side of the decay heat removal
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pumps is not physically located in an easily accessible area.
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The licensee has redesigned the method of measuring the bor-i ated water flow for hot leg recirculation in the system, following a LOCA, by using a remotely monitored ultrasonic measuring device.
61, Paragraph 6.3.1.3, describing this new method.The licensee ha The equipment has been ordered but not delivered as of this inspection period.
This item is considered to be u' 9 solved pending inspection of the completed work and review at the acceptance data by an NRC inspector (78-06-08).
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6.
Review of Nonroutine Events Reported by the Licensee Reference 10 CFR 50.55(e) report letters dated August 8,1975, a.
and April 8,1977, concerning concrete block walls not designed for seismic loads.
The inspector reviewed ECM 2833, Revision 4; ECM 3214, Revision 5; and ECM 3299, Revision 1.
These documents were properly revised and signed by Quality Centrol Engineers.
Also, DR 0847 was reviewed and was found to be preparly dispositioned.
The inspector reviewed ECM 5165 Revision 3, ECM 5213 (original issue), ECM 5265 Revision 4,.ECM 5250 Revision 6, DR 0840, and EDR 4376. The structural work is complete.
The work required under EDR 4376 has not been completed.
i The inspector performed a visual inspection of the in-place i
structures. The inspector had no further cuestions regarding this item.
b.
Reference 10 CFR 50.55(e) report, letter dated September 17, 1976, concerning the diesel generator b~ ilding room ventila-u tion system, was reported to be undersized to maintain a specified engine room temperature.
The inspector reviewed reports P-5026 (FCR 2340.1), CI-17 (FCR 2340.2), and P-5029 (FCR 2340.3).
Punch list items on P-5026 and on P-5029 remain open but within the licensee's control.
The functional test, TP-176/2, was conducted to test the operation of fans, dampers, thermostats, interlocks, and time delays.
The test has been completed, reviewed, and approved.
The inspector had no further questions concerning this item.
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c.
Reference 10 CFR 50.55(e) letter dated October 31, 1977, con-cerning failure of GE Type SBM switches.
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The inspector reviewed the licensee Problem Report (PR-2393)
issued on November 17, 1977, which defined the SBM switch
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problem. A listing of SBN switches was attached to the pro-
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blem report with testing and quality control requirements defined in the attachment.
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The Quality Control organizatien witnessed and recorded the following tasks on QCIR (PR-2392):
Switch Operation
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Wiring Connections
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Replacement Location
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Item test (New)
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Item test (Original)
Location
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The QCIR reports covered the following dates:
1/11/78,12/23/77, 12/22/77, 12/21/77, 12/15/77, 12/14/77, 12/13/77, 12/12/77, i
12/9/77,12/8/77,12/7/77,12/5/77,12/2/77,11/30/77, and 11/29/77.
Licensee Memorandum TMI-11-5985 dated October 4, 1977, defining the SBM Switch replacement effort and drawing 3075, sheet 18, were reviewed by the inspector.
The above QCIR reports covered the requirements of the October 4, 1977 memorandum.
The inspector had no further questions on this matter.
d.
Reference the licensee's report of a significant deficiency in the design of 120 Volt AC Vital Power Inverters in accordance with " CFR 50.55(e).
The inspector reviewed the Field Change Request Number (FCR 2383.1) dated June 13, 1977, which describes the installation of additional circuit components and design modifications cf the existing wiring in vital power units 2-1V through 2-5V per PCN 2383.
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The design change added a voltage sensing board B/M item #1 reference sketch SK-2383.1 Sheet 7, to the 15KVA Static Switch
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hardware design.
The sensing board was designed to control the 120 VAC output to + 3% of nominal voltage. A TD relay RL/30 was rewired to tee requirements of drawing SC1 DWG-8&R File No. 35A-00-0009 Sheet 1 and 2.
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The power inverters were retested to the requirements of TP 400/1.
The inspector reviewed the test data results and determined that they complied with the requirements of the Test Procedure 400/1.
The inspector had no further questions on this matter.
7.
Licensee Action on IE Eulletin/ CircularsBulletin 77-02, Potential Failure Mechanism in (W) AR Relays with Latcn Attacnments Reference letter dated October 10, 1977, response indicating that the subject relays are not installed at TMI-2.
Based on discussions with the licensee and a review of drawings, the inspector has no further questions concerning this item.
8.
Licensee Action on Previous Inscection Findings (Closed) Unresolved Item (320/77-45-01):
Eddy Current Inspection of Steam Generator Tubes. The licensee has completed the " Eddy Current" examination of 100 percent of both A and B steam generator tubes. This examination revealed the following anomalies. Twenty two tubes in "B" generator and ten tubes in
"A" generator were detected with wall reductions greater than 40 percent.
The licensee has taken corrective action by removing four tubes (reference: inspection report 50-320/77-46 for location) for laboratory analysis and plugging the 32 tubes described above.
In addition, 5 additional tubes were plugged for varicus reasons.
The licensee has determined that the cause of the wall reduction was associated with the steam generator fabrication.
The licensee has determined that the steam generators meet the requf rements of Regulatory Guide 1.83.
The iaspector had no further questions at this time.
9.
Unresolved Ite s_
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Unresolved items are matters about which more infomation is required in orde-to ascertain whether they are acceptable items, items of noncomp iance, or deviations. Unresolved items disclosed du-ing the inspection are discussed in Parat 2phs 4 and 5 of this report.
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10.
Exit Interview The inspector met with licensee representatives (denoted in Para-graph 1) at the conclusion of the inspection on January 19, 1978.
The inspector sum.arized the scope and findings of the inspection.
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