IR 05000320/1978007
| ML19220C267 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 02/24/1978 |
| From: | Davis A, Kellogg P, Nicholas H NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19220C261 | List: |
| References | |
| 50-320-78-07, 50-320-78-7, NUDOCS 7904300113 | |
| Download: ML19220C267 (18) | |
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U.S. NUCLEAR REGULATORY COMMISSION
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OFFICI 0F, INSPECTION AND ENFORCEMENT Region I Report No.
50-320/78-07 Docket No. 50-320
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Category B-1 License No.
CPPR-66 Priority Metropolitan Edison Company Licensee:
P. O. Box 542
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Reading, Pennsylvania 19603 Three Mile Island Nuclear Station, Unit 2 F.tcility Name:
Inspection at:
Middletcwn, Pennsylvania i
Inspection conducted:
January 24-27, 30 - February 3, 1978 d2-v/7 9
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dd Inspectors: k * e,MS9f*"f1'"*P*'*"
$*/d)9"O actor Inspector ddtp signed H. pi ol,a,
2 /: 4 /W hr
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da'te sfjped T@.P.ebplowski,ReactorInspector 2/ W/z/
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date sig'ned Reactor n pector A.fTpkel bi / /Y/Wnn Qi&00~?/
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ReacprIn)pectoV
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nd L. Gage, R ctor Inspector date signed h )M l2W/~77 Approved by:
A. B. Davis, Cnlef, Reactor Projects Section date signed No.1, RO&NS Branch Insoection Summary:
24-27, 30 - February 3.1978 (Recort No. 50-320/78-07)_
Insoection on January Routine, unannounced inspection of licensee's action on Areas insoected_:
previous inspection findings; Fire Prevention Program; Fire Fighting Training; plant tour; review of overall startup test program; review of actions on Bulletins and Circulars; preoperational test results evaluation and test The inspection involved 179 inspector-hours onsite results verification.-
by six NRC inspectors and accompanying personnel.
No itcm of noncompliance were identified.
Results:
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iL Region I Form 12
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(Rev. April 77)
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7 904300113
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DETAILS 1.
Persons Contacted Metrocolitan Edison Comoany Mr. R. Bensel, I&C Engineer Mr. M. Bezilla, PORC Secretary
- Ms. L. Fisher, Fire Protection Engineer
- Mr. E. Gee, Safety Supervisor Mr. J. Hilbish, Senior Reactor Engineer
- Mr. G. Miller, Station Superintendent
+*Mr. J. Seelinger, Unit Superintendent, Technical Support Mr. R. Zechman, Acting Suoervisor, Training General Public Utilities Service Cerooration Mr. G. Delp, Mechanical Advisor
+*Mr. R. Fenti, Lead Site QA Auditor Mr. C. Gatto, Lead Mechanical Engineer
+Mr. T. Hawkins, Assistant Test Superintencent
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Mr. S. Levin, Project Engineer i
Mr. P. Marish, Electrical Supervisor
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+*Mr. M. Nelson, Technical Engineer Mr. I. Porter, Lead Engineer
- Mr. R. Toole, Test Superintendent Other Accomoanying NRC Personnel
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Mr. A. B. Davis, Chief, Projects Section No.1, Reactor Operations and Nuclear Support Branch
- denotes those present at exit interview on January 27.
+ denotes those present at exit interview on February 3.
2.
Licensee Action on Previous Insoection Findinas (Llosed) Inspector follow item (320/76-00-02, 320/76-09-01): Response i
time testing for engineered safety system. The inspector reviewed Test j
Precedure 310/3, and 315/1 results.
These procedures demonstrated the response times of the Engineered Safety Systems to be within the times required by the proposed facility technical specifications.
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.... _ _ _ (Closed) Unresolved item (320/77-01-01): CRPM procedures revision.
TP 330/3A, draf t 3, was revised to include the actual latching current to be utilized.
Procedure GP0031 does not (Closed) Unresolved item (320/77-03-11)GP0031 has been cancelle GP0061,
address record receipt control.
Correspondence Control, GP0062, Control File Index and GP0063, Record These procedures do address record receipt Control have been issued.
control.
(Closed) Unresolved item (320/77-26-20): CILRT procedure deficiencies.
The licensee has corrected temperatures, pressures, humidities and verification test data for instrument error and used these corrected l
values to calculate the test 'eakage rates.
LLRT additions to CILRT.
The (Closed) Unresolved item (320/78-05-02):
inspector reviewed local leak rate test results for SAV-20 and pene-tration R-562C.
Total leakage was less than 0.000001 %/ Day and was
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l added to Type A test results.
Sump level corrections to (Closed) Unresolved item (320/78-05-03):A review of the sump level CILRT.
showed that no correction to the ILRT results was required for sump level changes.
Calibration records. The (Closed) Unresolved item (320/78-05-04):
inspector reviewed licensee data on calibrations conducted on the dewccis and flowmeters after the ILRT and had no further questions in this area.
Satisfactory completion of (Cl ased) Unresolved item (320/78-05-01):The inspector reviewed '.
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CILRT.
Containment leakage rate by the pendently calculated the leakages.
mass point technique at the 95% upper confidence level is 0.0951 %/ Day.
This is below the acceptance criteria of 0.0975 %/ Day and indicates an acceptabic test.
(Closed) Unresolved item (320/77-28-05): Review drawdown test res TP 204/3 was evaluated for test results with respect to the drawdown of the sodium hydroxide tt'k.
Findings were acceptable.
(Closed) Unresolved item (320/77-32-02): Concrete surface temperatures on shielding greater than 150 degrees. The temperature charts from recorder AH-YMTC-5017 were reviewed for the period of August 15 through 10, 1977.
No shielding temperatures in excess of 1500 were SeptemberSeve-al temperatures were recorded in excess of 1500 but the noted.
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points were not on shielding.
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(Closed) Unresolved item (320/77-40-01): Resolutica of concerns on soluble poison concentration test. The ccmpleted test TP 600/3 was reviewed and the concerns noted in the referenced report had been satisfactorily addressed.
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Reactor coolant pump (0 pen) Inspector follow item (320/77-40-02):
lne volute seals on all tour reactor seal leakage at loop volute.
coolant pumps have been replaced and tested by applying pressure between the seals. This item remains open pending final leak check-ing at normal operating temperature and pressure.
(Closed) Inspector follow item (320/77-41-01): Maximum core flow acceptance criteria bases. The licensee has cbtained a new maximum core flow acceptance criteria from the NSSS.
This new criteria indicates a maximim expected flow rate of 293,600 gpm.
This new criteria has been incorporated into TP 200/11 and does take core stability,and lift into consideration.
(Closed) ' Inspector follow item (220/77-41-08): TP 330/5 control rod drive trip test.
Draft 3 of TP 330/5 was approved by the TWG on January 23, 1978.
This draft had been revised to include the require-ments for inverse count rate plots, audible count r::ta monitoring and caution statements.
(Closed) Unresolved item (320/78-06-06): Electrical penetrations.
The inspector examPned the installation of the electrical cat,les leaving cable tray 3105 and entering the electrical penetration number E34.
The electrical cables were supported by brackets tied to the tray support.
The licensee was hand wiring selected electrical containment penetration circuits in accordance with the requirements outlined in Field Change Report (FCR 2453.2) dated January 26, 1978.
Qu.ility Control was verifying each splice on a 100% inspection basis.
The inspector examined the corrections on electrical penetration 607. The cuality
. control records verified that the work was in accordance with the requirements of FCR 2453.2.
(Closed) Unresolved item (320/78-06-04): Fire stops and seals for walls and floors. The inspector examined the fire stop and seals material installed in the following areas:
~ Diesel Generator Rooms
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Diesel Generator Fuel Oil Storage Tank Area
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Battery Rooms
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Battery Chargers and Static Inverters.
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O7 U t The inspector examined the Cheatrol Completion Form which was used by the licensee to verify that area work was completed.
Open items estab-lished during the area acceptance were noted on the form.
Quality control was verifying work as it was completed.
The following areas were accepted with noted open items documented.
Turbine Building, dated Sanuary 19, 1978
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Auxiliary and Fuel Building, dated January 27, 1978
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Controi Building, dated January 23, 1978
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Service Building, dated January 26, 1978
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Diesel Generator Building, dated January 24, 1978
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River Water Pump House, dated January 6,1978.
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(Closed) Unresolved item (320/78-06-05): Cable spreading room.
The inspector examined the installation of the structure around the 4.16 KV bus duct in the cable spreading room and determined it was installed
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in accordance with the engineering drawings.
The work was inspected j
by quality control.
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Fire Prevention Proaram
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Technical Soecification Surveillance Tests The inspector reviewed the results of the surveillance tests per-formed'en fire prevention / protection equipnent in accordance with the December 16, 1977 issue of Appendix "A" to the licensee's Technical Specifications.
Satisfactory results were found for the following surveillance tests:
Spec.
Test Report -
Date of Para. No.
No.
Comoletion 4.3.3.8.3 2332-M3 1/19/78 5.7.10.1.1.a 2331-W1 1/25/78 4.7.10.1.l. b 3303-Ml 1/16/78 4. 7.10.1.1. d 2333-Al 11/17/77 4. 7.10.1.1. e.1 2333-R1 11/15/77 4. 7.10.1.1. e. 2 2333-R5 1/19/78 4. 7.10.1.1. e. 3 3303-R1 1/18/78 4. 7.10.1. 2. a 3303-M1 1/16/78 4. 7.10.1. 2. c.1 3301-Rl 9/16/77 4. 7.10.1. 2. c. 2 3303-Rl 1/18/78 4. 7.10. 3.1. a 2331-SA2 9/1/77
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4. 7.10. 4. a 2331-M1 1/23/78
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The remaining surveillance tests (in specification paragraph 4. 3. 3.8, 4.7.10.1, 4.7.10. 2, 4.7.10.3, 4.7.10.4, a nd 4.7.11) either had not been performed or had not yet been filed numbers
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at the time of the NRC inspection.
This item is considered unresolved, pending a review of the results of the remaining surveillance tests, by an NRC inspector, during a subseqQent inspection.
(320/78-07-01)
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b.
Work Control Procedures The inspector verified that there is a work-control procedure which defines requirements for operations personnel approval and It is Station Administrative control of modification activities.
Procedure 1021, " Plant Modifications," Revision 0, dated July 22, Work requests that affect nuclear safety or are required to minimize radiation exposure must have the Unit Superintendent 1977.
approval.
The licensee's " Safety Policies and Procedures Manual" contains a section titled Welding and Cutting Procedure (Fire Safety),"
26, 1975, that describes the special authorization dated June that is required for activities involving open-flame sources.
It also requires tne assignment of a " fire watch," during these activities.
Quality Assurance Surveillance Procedures c.
The inspector verified that there are quality assurance procedures that require periodic surveillance and audit of authorized modi-fication and maintenance activities to verify ccmpliance with established controls. The procedures incidde:
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GP 4016. "OQA Audit Program," Revision 3, Change 7, dated
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December 27, 1977.
GP-1008, " Systems Lists," Revision 1, Change 6, dated
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January 4,1978.
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Desian Controls for Penetration Seals d.
The inspector verified that procedures have been prepared which specify the type of cable penetration-sealing materials, to preclude the use of fismmable materials when sealing safety-related cable penetrations in walls and floors. The procedures include:
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Chemtrol Corp. Procedure 3350. " Installation of CT-18
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Silicone Foam" Chemtrol Corp. Procedure 4001, " Installation of Firewall
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50" The inspector samoled wall and floor penetrations for safety-related cables and found them to be sealed in accordance with procedures 4001 and 3350.
4.
Fire Fichtina Procedures, Trainina and Orills a.
Procedures The inspector verified that the licensee had established procedures for fire control. The procedures include:
AP-1004, " Fire Emergency Plan," Revision 3, dated June 20,
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1977 AP-1038, " Administrative Controls -- Fire Protection Program
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Plan," Revision 0, dated December 29, 1977
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2202-3.1, " Fire," Revision 0, dated June 13, 1977
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2104-6.1, " Fire Protection System," Revicion 2, dated
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January 12, 1978.
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b.
Trainino The inspector verified that all members of the licensee's Fire The licensee's Brigade received fire' Prevention / protection training.
computer printout titled " Staff Training Status" (latest edition dated December 1,1977), lists the plant personnel and the type
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(and date) of training each person received.
c.
Drills The inspector reviewed the reports of the licensee's fire drills which verified that station fire drills were conducted once per month throughout 1977. The most recently documented drill, con-ducted December 29, 1977, involved members of the local volunteer fire departments. Three V.F.D.s responded: Londonderry, Bainbridge, and Middletown.
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d.
Fire Insnection Report The inspector reviewed the most recent fire inspection report of the Nuclear Energy Liability)- Property Insurance Association (tha 23, 1977. The-report contained five new recomendaticns, one of which affected safety-related equipment.
The licensee had taken action on this item.
e.
Frercency Shutdown Procedures The inspector verified that there are plant procedures that provide alternate methods for accomplishing an orderly plant shutdown and
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cooldown in case of loss of nonnal coolant supply systems.
The procedures include:
2102-3.3, " Decay Heat Removal Via OTSG," Revision 3, dated
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November 15, 1977 2104-6.3, " Emergency Feedwater," Revision 2, dated
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Decenbe-12, 1977 2202-2.1, " Station Blackout," Revision 4, dated January 12,
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1978 2202-2.5, " Station Blackout with Loss of Diesels," Revision 3,
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dated January 5,1978 2202-1.3, " Loss of Raactor C~-Snt/RCS Pressure," Revision 3,
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dated December 30, 1977 2202-1.4, " Loss of RC Flow /RC Pump Trip," Revision 2, dated
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November 28, 1977 2202-2.2, " Loss of Steam Generator Feed," Revision 0, dated
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February 24, 1977 2202-1.8, "I.oss of Decay Hest Removal," Revision 2, dated
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January 5,1978 2203-1.5, " Loss of RC Makeup," Revision 0, dated February 24,
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Facility Inspection The inspector conducted an inspection of the facility, including the Control Room, Cable Spreading Rooms. Battery Rooms'. Diesel Generating Rooms, Auxiliary Building, Turbine Hall and outside hydrants and hose stations. The inspector noted the following:
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Clean-uo_
Flamable debris, resulting from final construction activities, must still be removed from all areas.
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Portable Fire Extinauishers Portable fire extinguishers must still be installed at all
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permanent extinguisher stations (replacing the temporary extin-guishers supplied during constructico).
Items a and b are considered unresolved pending a subsequent inspection of the facility by an NRC inspector.
(320/78-07-02)
6.
Overall Startuo Test Prooram Review a.
Purcose The inspector conducted a review of the overall startup test program organization and administrative controls for Three Mile Island Unit 2 to verify conformance with regulatory requirements.
b.
References The following references were used for this review:
(1) Test Manual for TMI 2, Revision 5,7/13/76 2) TMI 2 Master Test Index, Revision TCN-20,12/22/77 3) TNI 2 FSAR Chapter 14
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TMI 2 Master Test Equipment List 5}; Regulatory Guide 1.68 c.
Scope
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The inspector verified administrative controls had been established and implemented in the following areas:
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(1) Test Proaram Verification that a description of the startup test General areas program was prepared by the licensee.
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of testing were identified and responsibilities were assigned for test performance and results eva tests and power ascension tests in conformance FSAR requirements; Verification that the test program included testing re-quirements ccnsistent with Regulatory Guide 1.69, in
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that tests identified by Regulatory Guide 1.68 were in-cluded, the tests were sequenced for perfo able performance; Verification that the format and content of startup test procedures are consistent with regulatory requirements.
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(2) Test Orcanization Verification that the licensee has been assigned overall control of startup test _ctivities;
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Verification that written instructions are provided for the interfaces between the operations and test organi-
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zations; Verification that organizational responsibilities are
established in writing, in those instances where inter-
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f faces exist.
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i (3) Test Procram Administration
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Verification that formal administrative measures were
established governing the conduct of testing, including:
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Methods to verify a test procedure is up-to-date prior
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to its use; Methods to assure test personnel are knowledgeable of test procedures and requirements;
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Methods to change test prccedures during testing;
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Criteria established for interrupting a test and
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for continuing an interrupted test; Methods for test coordination;
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. Methods to document significant events and unusual
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conditions; Methods for identifying deficiencies and documenting
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their resolution and retest requirements.
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Verification that formal methods were established for con-trol of tast scheduling;
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Verification that formal requirements for evaluation of test results were established to provide for the following:
Test data reduction;
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Test results checked against previously established
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acceptance criteria; Deficiancies ar.a clearly identified and corrective
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actions reviewed and cmpleted; Retest requirements are established to verify accept-
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able system performance after corrective actions or modifications are completed; Test result evaluations are reviewed by appropriate
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licensee and contractor personnel, including those personnel responsible for approving the original test procedure.
(4) Document Control Verification that formal administrative measures have been
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established which control test procedure review, approval and issuance; Verification that formal controls were established to control
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revisions to approved procedures, including:
Review and approval conducted by group and individuals
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who issued original procedure;
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Control over obsolete procedures;
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Operating procedures to be'used during the testing approved in accordance with the Technical Specifi-
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cations; Responsibility assigned in writing to assure controls
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established above are implemented.
(5) Test and Measurement Eouioment Verification that administrative controls are established
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for special test equipment and include:
A listing of test equipment, calibration requirements
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and calibration history; l
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Controls for storage and issuance of equipnent to preclude use of equipnent that is out-of-calibration;
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Requirements established for recording test equip-
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ment identity and calibration date in test procedures to allow. etesting, if necessary.
d.
Finding No items of noncompliance were identified.
The inspector noted that no provisions were incorporated in the zero power test program for performing flux measurements as specified in Regulatory Guide 1.68, Appendix A, C.l.h.
In that the fixed
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incore detector system used at the facility was not designed for use during low power operation (<5%FP) the inspector had no further comments on this item.
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The inspector noted that in Appendix A, paragraph D.l.r of Regu-latory Guide 1.68, a requirement exists for comparing safety re-lated parameters calculated by the process computer with measured values. The inspector noted that nr one procedure exists to satisfy the above requirement.
However, several test procedures are per-formed during which hand calculations are canpleted and used to verify plant computer calculated values.
The following procedures fit this category:
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~ 800/11 TP 800/24 Ti'
ifl8 TP 800/31 1. 800/21 TP 800/33 TP 800/22 Since this area will be reviewed as part cf the routine inspection of the startup test prrgram, the inspector had no further questions on this item at this time.
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7.
3ulletins and Circulars a.
Licensee actions concerning the following Bulletins were reviewed:
71-04 Calculational Error Affecting the Design Performance of a
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System for Control?ir.g pH of Containment Sump Water Following a LOCA.
77-05 Electrical Connector Assemblies.-- 77-05A Electrical Connector Assemblies.
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These Bulletins were reviewed to verify:
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Licensee management forwarded a copy of the response to
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appropriate onsite management; Information discussed in the licensee's reply was accurate;
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Corrective action taken was effected as describe,d in the
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reply; and The licensee's reply was within the required time period.
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The review included discussions with licensee personnel, plant operating procedures and design drawings.
Findings were acceptable.
b.
Licensee actions concerring the following IE Circulars were reviewed:
77-01 Malfunctions of Limitorque Valve Operators
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77-04 Inadequate Lock Assemblies.
77-08 Failure of Feedwater Sample Probe.
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77-10 Vacuum Conditions Resulting in Damage to Liquid Process
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Tanks.
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77-11 Leakage of Containment Isolation Valves with Resilient
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77-13 Reactor Safety Signals Negated During Testing.
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77-15 Degradation of Fuel Oil Flow to the Emergency Diesel
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Genera tor.
- This review included discussion with licensee personnel, Plant Operation Review Lomittee Minutes,' operating procedures, surveillance procedures, maintenance procedures, administrative procedures and engineering drawings.
Findings were acceptable.
Additionally, with respect to IEC 77-13, the inspector verified the
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licensee had reviewed maintenance, surveillance and operating procedures to detemine if the limitations and restrictions for various plant conditions were identified.
No inadequacies were no ted.
Craft and operator training was reviewed to verify that system interactions were addressed.
Findings were acceptable.
8.
Preocerational Test Results Evaluation The inspector conducted an evaluation of the following tests.
TP 150/2 Reactor Building Structural Integrity Test (MTX 133.3)
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TP 150/3 Reactor Building Initial Leak Rate Test (MTX 133.4)
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TP 160/2 Reactor Building Air Cooling Functional Test (MTX 134.4)
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TP 172/2 Control Building Ventilation Functional Test (MTX 33.6)
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TP 180/3 Fire Protection System Functional Test (MTX 75.6)
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TP 204/3 Reactor Building Spray System Functional Test (MTX 141.6)
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TP 256/4 Loss of Instrument Air Test (MTX 90.7)
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TP 330/4 Integrated CPD System Test (MTX 38.6)
TP 380/1 Comunications System Functional Test (' TX 219.25)
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TP 400/1 Vital Power Supply Functional Test (MTX 213.2)
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TP 310/3 SFAS Actuation and Detection Test (MTX 160.3)'
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TP 315/1 Safety Related Instrumentation Response Time Testing (MTX 160.4)
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TP 600/3 Soluble Poison Concentration Control Test (MTX 147.10)
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TP 600/21 Integrated Safety Features (MTX 160.5)
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The test results were evaluated to verify that:
Test changes had been approved in accordance with administrative
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procedures, properly entered into the procedure, accomplished if actions were necessary, and did not change the basic objectives of the test; Test deficiencies had been resolved, accepted by appropriate
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management, retest conducted if required, and any system or process changes necessitated have been properly documented and reviewed; Test summaries and evaluations had been performed by the
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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 individual test steps and data sheets have been properly initialed and dated; Quality Assurance inspection records have been completed te
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document the adequacy of the test package contents, to indicate
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independent review of test records and data package contents, and an independent audit was performed during test performance as required by administrative procedures; and.
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 off site review committee has audited the test package, that their coments are included and corrective action has been taken if required.
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The inspector used one or more of the following acceptance criteri.3 for the above items.
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 Test Instruction 13. Test Interface Instructions
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Test Instruction 18, Test Procedure Documents
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Regulatory Guides Inspector Judgment
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Quality Assurance Program
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Findings were acceptable, unless noted otherwise below, The inspector noted that testing associated with the Feedwate Latching System in TP 315/1 was incomplete.
Completion of this
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i item is required prior to plant heatup ar.d this area will be reviewed on a subsequent inspection.
(320/78-07-03)
The inspector noted that a summary of RPS and SFAS channel response b.
times were being ccmpiled which would provide the total channel response time and demonstrate channel operability in accordance with, the Technical Specification requirements. The inspector stated that this item would be reviewed prior to plant heatup.
(320/78-07-04)
Problem Report PR 2568 was issued by the licensee to resolve c.
deficiencias identified during the performance of TP 600/21 and TP 310/3 (Deficiency 01:45 of TP 310/3 and Exception E-24, D-68, D-71 ar.d D-78 of TP 600/21).
The deficiencies are associated with room status board position indications for various safe-control guard related components (AH-V60, AH-V72, AH-V104, etc.).
Com-pletion and satisfactory resolution of this item is required prior to plant heatup and this area wdll be reviewed on a subsequent inspection.
(320/78-07-05)
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The diesel load sequence relays were tested in TP 310/3 to demon-d.
strate that engineered safeguard loads can be sequenced onto the emergency buses within specified time intervals.
The inspector noted that, in accordance with the proposed TMI2 Standard Technical Specifications dated December 16, 1977, the load sequence times for relays TDlA, TDA, TDlB and TDB were not within the requir '
tolerances. The insoector discussed sequencer operabiiig e-quirements with licensee representatives. The licensee stated that the sequence relay test results would be further reviewed. This item (320/78-07-06) is unresolved pending NRC: Region I review of i
the licensee's actions in this area.
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9.
Preccerational Test Results Verification The inspector conducted a review of the following test results.
TP 151/1 Reactor Building Isolation Valve Leak Rate Test (MTX 133.5)
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TP 171/2 Control Building Area Ventilation Functional Test (MTX 32.6)
TP 176/2 Diesel Generator Building Ventilation functional Test
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(MTX 5'.4)
TP 230/1 Rad Waste Disposal (Misc Liquid) Functional Test (MTX 125.6)
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TP 235/9 Dic5el Generator Building Sumo Test (MTX 54.6)
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TP 266/4 Nuclear Service River Water System Functional Test (MTX 111.6)
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TP 301/3C Nuclear Instrumentatio.n Pre-op Calibration (Power Range)
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(MTX108.4)
SP 320/3 ICS Interface Test (MTX 91.3)
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The test results were reviewed to verify that:
Test sunnaries and evaluations had been perfonned by the cognizant
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engineers, and test results had been compared with established acceptance criteria; and, Aporoval of the test results by those personnel charged with
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responsibility fer review and acceptance has been documented, and if the off site connittee has audited the test package, that their concents 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 Judgment
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- ' Quality Assurance Program Findings were acceptable.
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Test Results Review - Partially Completed Preocerational Tests _
10.
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 partial complete preoperational tests; TP 160/3 Reactor Building Emergency Cooling Functional Test TP 203/4 Decay Heat Removal System Fun
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(MTX 135.6)
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Test (MTX 110.6)
TP 401/1 Diesel Generator Functional Test (MTX 51.25 TP 120/5 Spent Fuel Handling Bridge Functional Test (MTX 73 TP 120/8 Fuel Transfer System and Miscellaneous Tests (MT
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TP 202/3 Makeup and Purification System
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TP 401/3 Station Batteries Discharge and Charge Test (MTX
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TP 301/2 NI Detector Cabling and Response
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SP-2 Filter Efficiency Tests MTX (Varied)
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All tests reviewed were completed to the extent that the functio testing will support Mode 6 operations.
The tests will be reviewed for completion of outstanding or unco testing at a _ subsequent inspection.
Unresolved Items _
11.
Unresolved items are matters for which more infon l
time is required in order to ascertain whether they are acceptab e, U items of noncompliance, or deviations.during this. inspe
.
Exit Interview 12.
The inspector met with licensee representatives (denoted in at the conclusion of the inspction on January 27 and Feoruary 3 The inspector sumarized the purpose and scope of the inspecti
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the findings.
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