IR 05000320/1978009
| ML19220B726 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 03/03/1978 |
| From: | Davis A, Kellogg P, Rebelowski T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19220B701 | List: |
| References | |
| 50-320-78-09, 50-320-78-9, NUDOCS 7904270256 | |
| Download: ML19220B726 (11) | |
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U.S. HUCLEAR REGULATORY CCP?.ISSION OFFICE OF INSPECTION ATID ENFORCEMENT Region *
Feport fic.
50 '20/78-09
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Docket No.
50-320 Category B-2 License No.
DPR-73 Priori ty
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Licensee:
Metrocolitan Edison Ccmr,v P. O. Box 542
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Reading, Pennsylvania 19603 Facility Name:
Three Mile Island Nuclear Station, t.' nit 2 Inspection at:
Middletown, Pennsylvania
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Inspection conduc+
Februar-10 and 13-14, 1978 3 2-7[
Inspectors:
-u Phylio g, Martor Inspector date/ signed h
s@st L4 Y3f7$
cats signed
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T. Rebelowski, Reac$br Inspector
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ask UMawn; W. Coleman, Reactor Inspector dat'e signed
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W t A ~.
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Tooin, ysical Security inspector date signed v#/
k Approved by:
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A. B. Davis, Chief, Reactor Projects date signed Sectio _n No.1, RO&NS Branch
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Inspection Summary:
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Insoection on February 6-10 and 13-14,1978 (Recort No. 50-320/78-09)
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Areas Inspected:
Routine, unannounced inspection of licensee's action on previous inspection findings; vibration assessment program; physical security; readiness for operating license issuance; inservice testina of pumps and valves; initial fuel load; test results review. The inspection involveif 71 insnector hours onsite by four NRC inspectors.
Results:
Of the seven areas inspected, no items of nonccmpliance were' identified j' six areas; one apparent iten of nonccmpliance (Infraction - failure to have a ible source range indication in containment - Paragraph 7.c) was identified in one area.
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7904270256 81 273
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DETAILS 1.
Persons Contacted Metrocolitan Edison Cemoany
+Mr. M. Bezilla, PORC Secretary Mr. J. Chwastyk, Shift Supervisor
+Mr. J. Floyd, Operations Supervisor
+Mr. J. Hillbish, Reactor Engineer Mr. B. Mehler, Shift Supervisor Mr. W. Ream, ISI Coordinator
- +Mr. J. Seelinger, Unit Superintendent, Technical Support Mr. D. Shamis, Engineer General Public Utilities Service Corocration
- Mr. J. Barton, Project Manager Mr. G. Delp, Mechanical Advisor Mr. R. Fenti Lead Site OA Auditor Mr. C. Gatto Lead Mechanical Engineer
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Mr. T. Hawkins, Assistant Test Superintendent Mr. C. Hubbach, OC Inspector Mr. M. Nelson, Technical Engineer Mr. S. Poje, Test Engineer Mr. I. Porter, Test Engineer Mr. R. Toole, Test Superintendent Mr. J. Wright, Site OA Manager
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- denotes those present at the exit interview on February 7,1978.
+ denotes those present at the exit interview on February 14,
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2.
Licensee Action on Previous Insoection Findinos (Closed) Unresolved Item (320/76-18-01): Training Program - Offsite Agencies.
The inspector reviewed the implementing procedures for the training of offsite agencies. The concerns noted in the refer-enced inspection report had been incorporated into the completed procedures.
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81 274
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(Closed) Unresolved Item (320/77-24-01):
Adecuacy of Station Emer-gency Plan Implementation.
The Station Emergency Plan and imple-
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manting procedures were reviewed to verify.that a state of adequate
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preparedness would ce implemented by the plan and procedures.
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inspector verified the plan covered all aspects of emergency planning as issued.
(Closed) Unresolved Item (320/17-47-05):
Verification of bolts used to fasten nice support plates.
The inspector reviewed the results of an inspettien of hanger anchor bolts conducted on February 3, 1978.
A random inspection of 99 anchor bolts for prcper lenoth by ultrasonics indicated all but two bolts had required enaaoement.
These two bolts were found to have less than minimum engagement by 1/4 inch and were subsequently replaced.
The program indicated a gross problem with anchor bolts did not exist.
l (Closed) Unresolved Item (320/77-47-06):
Clarification on method of
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fastening mechanical snubber plates.
Th; licensee reviewed the plate screw question and replaced all plate screws with screws of
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sufficient length to penetrate the plate.
These new screws addi-tionally were lock wired in place.
The inspector verified completion of this program by direct observation of several snubbers in the reactor and auxiliary building.
i (Closed) Unresolved Item (320/77-47-08):
Retaining rcrews on mechan-ical snubber shield. The licensee's review of the screws on the snubber shicld indicated the screws and shield did not affect the
' operation of the snubbers.
Based on this evaluation the licensee determined there was no need to insure the screws were positively restrained.
(Closed) ~ unresolved Item (320/78-02-01):
Locking doors of emeroency diesel generator building. The inspector verified the doors of the emergency diesel generator building had been locked.
(Closed) Unresolved Item (320/73-02-02): Alarming protected area fence. The inspector verified the required alar s were present and activated.
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81 2,75
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(Cicsed) Unresolved Item (320/78-06-01):
Loose screws and bolts
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I on pipe hangers and supports.
Quality Control inspectors have been instructed to inspect the general areas as the inspections for reworked items are being conducted.
This program as well as the licensee's surveillance program on hangers will ensure these items are ider.tified and corrected. The other items noted were corrected or the drawings have been modified to show the as-built condition.
(Closed) Unresolved Item (320/78-06-02):
Pipe hanger and supports not installed in accordance with drawings. The drawings have been modified to show the as-built conditions.
This modification to
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the drawings was in progress during the inspection.
(Closed) Unresobed Item (320/78-06-03): Helds on pipe sup p rts.
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The licensee's review of weld histories and vendor information indicated the welds to be acceptable as installed.
(Closed) Unresolved Item (320/78-06-07): Add protection of 4.16 KV bus and separation of table trays.
Quality Control inspection of the installation of the fire barrier material was completed on February 7, 1977. Additionally, all rework associated with this
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inspection was completed at this time.
(Closed) Unresolved Item (320/78-07-02): Cleanup of flamable debris and installation of portable fire extinguishers.
The inspector toured the reactor, auxiliary, and control buildings to verify the i
facilities readiness to load fuel.
Portable fire extinguising equipment had been installed and flammable debris had been removed.
3.
Vibration Assessment Procram
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References:
(1) TMI-2 Procedure No. 2502-1.15 Inspection of Reactor and Vessel Internals (2)
Reg. Guide 1.20 Section D.2, December 1971 (3) FSAR SuppTement 2, 41.7/14.1.1 (4) FSAR Supplement 2,11.6/3.9
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(5)
IE Inspection Report 50-320/77-42 (6) Reg. Guide 1.68
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a.
Insoection of Reactor and Vessel Internals The licensee has completed the inspection of the Plenum Assem-bly.
The procedure No. 2502-1.15 has the followino outstanding
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items to be completed prior to Head Closure, Item D-8, B-12 A-1, A-4, and A-ll, These items will be reviewed at a subse-quent inspection.
This item is unresolved.
(78-09-01)
b.
Precoerational System Testina Vibraticn Assessment Regulatory Guide 1.68, Appendix A, Section
,, Preoperational
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Testing, addresses the monitoring of components such as pipino systems, heat exchangers, and rotatino machinery for excessive vibration.
During the preoperational test procram conducted by the licensee, the following tests were monitored for vib a-tion baseline data:
TP 202/3, Makeup and Purification System Functional Test
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(MTX 99.6);
I TP 202/7, Makeup and Purification System SF Test (MTX
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99.7);
TP 203/4, Decay Heat Removal System Functional Test (MTX
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47.9);
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TP 203/7, Decay Heat Removal System SF Test (MTX 47.10);
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TP 204/3, Reactor Building Spray System Functional Test
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(MTX 141.6);
i TP 240/3, I..termediate Closed Cooling Water System Functional
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l Test (MTX 92.6);
j TP 264/4, Decay Heat Closed Cooling System Functional
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Test (MTX 46.6);
TP 266/4, fluclear'ervice River Water System Functional S
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Test (KTX 111.5);
TP 267/4, Nuclear Service Closed Coolina Water System
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Functional Test (MTX 110.6); and.
TP 600/4, Makeup and Purification System Operational Test
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(MTX 99.8).
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i 81 277 i
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No inadecuacies were found during the inspectors' review of the licensee's test results in the area of vibrational data or
visual observance of systems.
The inspector has no further questions in this area.
4.
Physical Security By letter dated January 24, 1978, the licensee submitted the Interim Physical Security Plan for Unit 2.
On January 27, 1978, Revision No. I was submitted.
The Plan has been found acceptable; however, the licensee has not received a formal acceptance as of February, 8,1978 from the Division of Licensing.
Two prior Region I Inspections (50-320/78-02 dated January 5-6, 1978 and 50-320/77-44 dated November 15-19,1977) have verified that the Security program being implemented is in compliance with those applicable portions of 10 CFR 73.55.
l During this Region I Inspection (50-320/78-09), the licensee was found to be in compliance with the Acceptad Plan.
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t 5.
Readiness for Operatina License Assuance The inspector reviewed the following to establish the facility's readiness for operating license issuance:
All uncorrected items of noncompliance and their status;
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I All unresolved items and their status;
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l All preoperational testing which was incomplete; j
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System perfomance deficiencies and their plans for correction;
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Systems for which construction was not complete;
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Incomplete work lists;
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Facility cleanliness; and,
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Flood protection devices available.
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The inspector determined that items remaining inccmplete or un-corrected would not affect the facility's ability to lo
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and have been included in the operating license.
6.
Inservice Testino of pumos and Valves of ASME Code Class 1, 2, and 3 pumps and valves.T has received a preliminary review and approval by NRP and has be This procram implemented by the licensee.
n During this review, the inspector discussed the implementation of program with the ISI coordinator and reviewed two test procedures e
(2303-M14 and 2303-07)for compliance with ASME Section XI requir ments.
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e-The licensee's program considers only Containment Isolation Val l
as Category A valves and tests these valves according to 10 CFR i
50, Appendix J requirements.
requirements which could cause a valve to be. Category A tested according to Section XI reouirements.
The inspector stated that future inspections will include the r
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of leak test procedures to verify that the progra
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eview a
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Within the scope of this reytew, the inspector found no inadequa in the licensee's program.
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Initial Tuel Load a.
_Prereouisites veillance requirements for enteriThe inspector chose a sam ng Mode 6 and reviewed
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completed surveillance data to verify that the surveillance items had been completed.
scope of this review.
The following table depicts the
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81~279
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B TS #
Surveillance Description Procedure *
Date Comcleted 4.9.2 SRM Functional Test 2303-W1 2/8/78 4.1.2.1 Baron Injection Flow Path 2301-M2 1/16/78 2301-U1 2/8/78 4.1.2.5 DHR Pump Operable 2303-M2 1/25/78 4.1.2.6 Boric Acid Pump Operable 2303-M26 2/2/78 4.1.2.8 Borated Water Source Avail-2304-W1 2/6/78 able 2601-Mi 1/30/78 Table Radiation Monitoring System 2302-R3 1/14/78 4. 3-3'
4.8.1.2 Shutdown Electrical Power 2301-W1 2/8/78 Systems
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4.8.2.2 Operable AC Busses 2301-W1 2/8/78 4.7.10.1 Fire System Operability 2331-R2 1/23/78
2333-Al 11/17/77
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2331-R1 1/8/78 3302-W2 2/1/78 4.3 3.3.1 Seismic Instrumentation 2303-SA1 1/30/78
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Functional Test 4.3.1.1.1 SR Neutron Flux Rate Cali-2302-Rl.7 12/20/77 bration 4.9.6 Fuel Handling Bridge Hoist 2315-R2 2///78 Test 4.9.4 Containment Penetrations 2501-4.lE 2/11/78 Closed or Operable The inspector had no further questions. on the above items.
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81 280
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b.
Fuel Loadinc Witness The inspector observed fuel handling activities in the control room at two different times, in the reactor buildino at two Addi-different times, and in the spent fuel area one time.
tionally the inspector observed portions of the repair and testing of the fuel transfer canal trolleys at two different times in the spent fuel area.
During one observation the inspector noted the conduct of a shift turnover in the cont-ol room.
By direct observation or record review the inspector verified that the following aspects of fuel loading met established requirements:
(1)
Constant communications between fuel loading stations; (2)
Fuel handling team manning met TS licensed operator requirements and. fuel loading procedure requirements;
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Inverse count rate plots were maintained in accordance with the fuel loading procedure; (4) Baron concentration was verified by analysis to be greater than 1800 ppm; (5) Access control to the refueling floor and the spent fuel pool were in accordance with the posted RWP; and, (6)
Refueling status boards were maintained in the control rocm in accordance witn the refueling procedures.
The inspector reviewed the working copy of the fuel loading procedure, the Shift Foreman's Log for the period February 10, 1978 to February 13, 1978, and the Control Room Operator's Log for the period February 7, 1978 to February 9, 1978.
The inspector discussed problem areas noted in the logs with licensee personnel and detemined that proper corrective or remedial action had been taken on each item.
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S1 281 t
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c.
Audible Count Rate During observation of fuel loading in the Reactor Building, the inspector did not hear the audible sotrce rance neutron instrument output as requireo by Technical Specification 3.9.2.
The Shift Supervisor stated that the operator per-forming the inverse count rate calculations was responsible to monitor the audible " growler" on the counter / scaler which was attached to the auxiliary neutron detectors.
Howeve.,
the responsible operator was not aware of the audible signal nor could he or the inspector adequately hear the output of the " growler." This item (320/78-09-02) is in noncompliance with Technical Specification 3.9.2.
The Shift Supervisor took immediate remedial action cn this item but the inspector stated that a better audible indication should be provided in the Reactor Building.
8.
Items Occurrino Durino Inspection During this inspection, the inspector was informed that the licensee had identified two items in which he violated Technical Specifica-i tions.
One item involved the failure to establish a fire watch
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after placing the Halon System in manual in accordance with TS 3.7.10.3, and one item involved the loss of audible count rate indication in the containment after unloading the auxiliary neutron detectors which were providing the required indication in accordance with TS 3.9.2.
The licensee took immediate corrective action on these items and made them the subject of a prompt licensee event report.
The inspector had no further questions on these items.
9.
Test Results Review - Partially Comoleted Preocerational Tests The licensee has tested and reviewed the test results by the Test Working Group Meetings for those systems that are required to be functional to support Mode 6 operation.
The inspector evaluated or verified the following partially completed preoperational tests:
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TP 120/6, Main Fuel Handling Bridge Functional Test (MTX
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78.7);
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TP 120/7, Auxiliary Fuel Handling Bridge Functional Test
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(MTX 78.8);
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TP 360/lA, Radiation Monitoring System - Atmospheric Monitors (MTX 123.2);
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TP 360/lC, Radiation Monitoring System Area Monitors
'"~,s 123.4); and,
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TP 600/5, Nuclear Chemical Additional and Sampling System Operational Test (MTX 15.7).
All tests reviewed were completed to the exte^t that the furctional testing will support Mode 6 operations.
Nc inadequacies were identi-fied. The tests will be reviewed for cor41etion of outstanding or uncomoleted testing at a subsequent inspection.
10.
Unresolved Items Unresolved items are matters for which more information or addi-tional time is required in order to ascertain whether they are acceptable, items of noncompliance, or deviations. Unresolved items disclosed during this inspection are discussed in Paragraph 3.
11.
Exit Interview The inspector met with licensee management (denoted in Paragraph 1)
on February 7 and 14, 1978, to discuss the findings of the inspec-tion. The item of noncompliance and requirements to monitor audible source range count rate in the control room and containment during Mode 6 were discussed.
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81 283
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