IR 05000320/1977029
| ML19220B441 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 08/19/1977 |
| From: | Coleman W, Kellogg P, Nicholas H NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19220B435 | List: |
| References | |
| 50-320-77-29, NUDOCS 7904260109 | |
| Download: ML19220B441 (9) | |
Text
U.S. NUCLEAR REGULATORY COPP.ISSION OFFICE OF, INSPECTION AND ENFORCEMENT Region I 77-29 Report'No.
Docket No.
50-320 Category
License No. CPP R-66 Priority
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Licensee:
Metropolitan Edison Ccraanv P. O. Box 542 Reading, PennsyTvania Facility Name:
Three Mile Island, Unit 2 Inspection at:
Middletown, Pennsylvania Inspection conducted: July 20-22, 26-28, 1977
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Inspectors:
if:3 xeneywsmgeactor Inspector date'sicned W,1q'J/WH /O Th li7 y
da te' signed 1/. 4oleman, neaztor Inspector Au o f ff /f7 7 d %-
dath sig/~7 ~7 f/n ;;ed L
cj rom, neactor inspector Q1 w fo (
vA I n ogg, neactor-Inspector date si~ned
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h. alcnolas, nea,ctor inspector date sigried date signed O
Approved by:
u. L. Lapnton, nlerfuclear support date signed Section No. 1, RO&N5 Branch Insoection Sum.ary:
Inscection on July 20-22 and 26-28.1977 (Recort No. 50-320/77-29)
Routine, unannounced inspection.of licensee action on previous Areas insoected:
inspection items; fuel inspection, asserbly and storage; initial fuel loading procedures; pipe support and restraint systems; test results verification; feed pump turbine overspeed trip settings; review of startup logs; preparations for hot functional testing; and site tour. The inspection involved 99.5 inspector hours on site by five NRC inspectors.
Of the nine areas inspected, one item of noncompliance was identified Results :
in the area of Fuel Storage.
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Region I Form 12
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(Rev. Aoril 77)_.
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RETAILS 1.
Persons Contacted Metrocolitan Edison Comoany
- Mr. M. Benson, Reactor Engineer Ms. M. Bezilla, FORC Secretary Mr. J. Haverling, Site Protection Supervisor
- Mr. J. Hillbish, Senior Reactor Engineer
- Mr. T. Mulleavy, Radiation Protection Superviscr Mr. R. Neidig, Q.C. Specialist General Public Utilities Service Corocration (GPUSC)
Mr. R. Fenti, QA Auditor Mr. C. Getto, Engineer Mr. Hawkins, Asst. Test Superintendent Mr. S. Levin, Project Engineer Mr. I. Porter, Engineer
- Mr. M. Nelson, Technical Engineer Mr. J. Roberts, Engineer Mir. R. Toole, Test Superintendent Burns and Roe Mr. G. Harper, Site Project Engineer Gilbert Associates Mr. J. Rcbison, Consulting Engineer Mr. G. Delp, Consulting Engineer United Enoineers and Constructors Inc.
Mr. G. Schmidt, Piping Supervisor denotes those present at exit interview July 22, 1977.
- denotes those present at exit interview July 28, 1977.
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Licensee Action on Previous Insoettion Findines (Closed) Unresolved item (320/77-03-10): Design changes to training:
AP 1021 and the design change form establishes procedures for the routing of design changes to training for appropriate revisions of the testing program.
This item 1s resolvec.
(Closed) Unresolved item (320/77-28-01): Acceptance criteria for boron concentration TP600/3.
Test Change Notice-1 has established a 10 ppm criteria for compariscn of calculated vs analytic results.
This item is resolved.
(Closed) Unresolved item (320/77-2S-02):
The licensee has referenced OP 2203-1.1 to address emergency boration section of TP600/3 soluble Poison Concentration Test.
This item is resolved.
(Closed) Inspector Followup item (320/77-01-03): The licensee has cocumented in Startup Problem Report 2262 his request for change to CRDM Technical Manual in the areas of CRDM latch, minimum run and dropout currents as noted in procedural review of TP330/3A. This item is resolved.
(Closed) Unresolved -item (320/75-17-09):
Diesel Generator Trips.
The licensee's present wiring diagrams and wire checks have been verified that the FSAR commitments in Amendment 54 (March 30,1977)
has been achieved.
This item is resolved.
(Closed) Unresolved item (320/77-28-07): RCS conditions for performance of TP600/13. The inspector's review of proposed Technical Specifi-cation 3/4.3.1 and 3/4.3.2 indicates that plant conditions for testing of Pressurizer Operational and Flow Test has been attained in the area of reduced pressures by R.P.S. instrumentation-action statement
- 2 and #10. This item is resolved.
(Closed) Unresolved item (320/76-15-02): The licensee's new fuel
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inspection procedure did not include detailed inspection guidance.
The inspector reviewed revision 3 of procedure 2501-6.1, Receipt, Inspection, Fit-up and Storage of New Fuel and Control Components, which included a new Attachment A, Guidelines for Inspection of New Fuel Assemblies.
This item is now resolved.
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Fuel Insoection. Assembly and Storace The inspector examined the following new fuel inspection a.
records to verify that inspection steps were performed, acceptance criteria was satisfied and that licensee audit findings had been adequately resolved.
(1)
Fresh Fuel Receipt Unloading Inspection Reports (2)
Container / Fuel Assembly Inspection Reports (3)
Fuel Handling Building Checklists (4)
QC Surveillance Reports for Receipt, Inspection and Storage of New Fuel Assemblies and Control Components (October 13, 1976 - May 18,1977).
No items of noncompliance were identified.
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The inspector toured the operating floor of the Fuel Handling Building to verify that license conditions were being satisfied and that storage conditions for the new fuel were adequate.
No inadequacies were identified with the following exception.
The inspector noted that there were no radioactive material
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caution signs posted on the doors leading into the new fuel
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storage areas as required by Title 10, Part 20.203(e)(1) of the Code of Federal Regulaticns. The curie content of the new fuel was verified to be in excess of 0.1 microcuries.
This item was identified to the licensee as an item of noncompliance.
(320/77-29-01)
The inspector requested to see fuel component and material c.
certifications plus vendor certifications of the availability
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of fuel manufacturing records. The inspector was informed that these records were located at the GPU offices in Parsippany, New Jersey.
Review of these records will be conducted during a subsequent inspection.
(320/77-29-C2)
4.
Initial Fuel loadino Procedures a.
Procedures Reviewed (1)
Procedure 2501-1.1, Fueling Control Document, Revision 0,
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June 20, 1977.
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0 Core Assembly, Revision 1, June 2,
(2) Procedure 2501-4.01, 1977.
Procedure 2502 ~i.14, Reactivity Insertion Computation, (3)
Revisien 0, November 2,1976.
Auxiliary Neutron Detector System, 2502-1.12, Procedure (4)
Revision 0, October 1, 1976.
Findines i
nts, b.
Procedures were reviewed for consistency with FSAR ccmm d standards.
regulatory requirements, ano applicable codes ments.
Procedures do not specify reactor vessel water level re-i quirements to be maintained during fueling operat ons.
(1)
A distinction is not made between the responsibilities o the Shif t Supervisor and the Fueling SRO.
(2)
l The procedures do not specify the calibration /functiona ce range testing requirerents for the auxiliary in-core sour (3)
neutron monitors.
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t Precautions, such as valve lockouts, to preclude inadv (4)
dilution are not specified.
Time limits for operators on shift are not specified.
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ih Radiological precautions for handling fuel assemblies installed Americium sources are not specified.
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Cross references to separate governing procedures (7)
consistently utilized.
be These items were acknowledged by the licensee and wi d res.
unresolved pending NRC review of the revised proce u (320/77-29-03)
i Pice Succort and Restraint Systems and Therral Excans on 21, 1977 (a) TP600/29 Thermal Expansicn dated April 5.
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(b) TP600/14 Pipe and Component Hanger Hot D
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References :
and Inspection Test dated April 7,1977 (c) MCP 15-2 Pipe Hanger Inspection (Draft)
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Scoce a.
The inspector reviewed the above procedure i
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tnertal expansion and pipe supcort inspections dur ng
' Functional Testing.
The planned program was reviewed to insure plans exi h
l the folicwing areas:
various temperatures to detect interference d and constant supports at predetermined te References (a) and (b) were reviewed with regard to procedure format, approval, FSAR test abstracts, and Findines_
b.
Reference (a) and discussions with test engineers revealed l growth all safety related systems which will experience therma f
ce will be " walked" throughout the heat-up to detect any inter eren This problems before the systems attain operating temperatures.
bbers, system walking is also designed to insure sp l
with respect to pipe and component supp the Essentially, pipe hangers, constant supports and snubbers are set at ambient temperature heat-up.
ports the design hot position for sprine, hangers and constant sup and for adequate remaining travel for snubbers.
h The inspector toured the reactor building aid observed tha in setting of spring hangers, snubbers and consta d com-spring hangers, five snubbers and five constant supports a progress.
The pared their positions wi.th the required design positions.
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inspector also noted the condition of several pipe sup
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component support structures.
er-was not evident on any of these ccmponents, and hanger pres vation was in progress.
No items of noncompliance were identified in this area.
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Startua Test Procedure Verification c.
The inspector briefly reviewed the licensee's plan for Precritical, Lav-Pcwer and Pcwer Ascension test procedures as defined in Regulatory Guide (RG) 1.68.
The review consisted of comparing licensee test procedures with those required by R.G.1.68 and cbtaining some reference material from the licensee for future in-depth review of these procedures.
No inadequacies were identified.
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Test Results Verification The test results of completed tests have been reviewed to determine that the licensee has:
Evaluated the test results to assure that the testing demon-
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strated that the systems met design requirements.
Test results were compared to acceptance criteria.
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A review of procedures has been in conforrance with Test Manual,
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Test Instruction No.18 Revision 5.
The approval of Test Working Group (TWG) which includes NSSS
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and AE representatives where indicated by the cognizance system under test.
The procedures verified include:
TP265/2 Circulating Water Functional Test (MTX 18.6) approved
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at TWG Meeting #70, June 30, 1977.
TP265/3 Amertap System Functional Test (MTX 1.6) approved at
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TWG Meeting #70, June 30,1977.
TP268/3 Secondary Service River Water System Functional Test
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(MTX 164.6) approved at TWG Meeting #54, March 17,1977.
- P268/4 River Water Chlorination Functional Test (MTX 155.6)
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agoroved at TWG Meeting of, October 7,1976.
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TP269/3 Secondary Services Closed Cooling System Functional Test
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(MTX 163.6) approved at TWG Meeting #59, April 21,1977.
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TP268/5 Screen House Services Functional Test (MTX 161.6)
approved at TWG Meeting #57, April 7,1977.
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TP305/l A Reactor Protection System Initial Power Application (MTX 151.2) approved at TWG Meeting #65, June 2,1977.
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TP255/3 Instrument Air Functicnal Test (MTX 90.6) approved at TWG Meeting #65, June 2,1977.
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TP350/1 Computer Hardware Verification (MTX 22.1 and 23.1)
approved at TWG Meeting #65, June 2,1977.
Findines The inspector identified one area of concern in his review of TP268/3 Secondary Service River Water System Functional Test.
The lubrication system to NSR, SR and SW pumps were to be modified to require the isolation of the domestic water system from the filtered water system (Problem Report 2108).
Isolation was to be acccmplished by a series of locked shut valves.
The inspector identified the need to effect positive isolation by means of capped or blanked piping.
The licensee stated that a modification would be made to effect this change. The inspector will review at a sub;equent inspection the completion of this change.
This is an inspectoi follow-up item (77-28-04).
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Steam Generator Feed Pumo Turbine Oversoeed Setting The inspector witnessed the initial settings of the overspeed trip of the SGFP Turbine (FM-U-1 A).
The house boiler supplied steam at 130 psig to roll the unit.
The testing was accomplished in a controlled ranner with vendor, AI and licensee's engineers in attendance, nonitoring vibration and speed control. Tne trip witnessed occurred
at s 5000 rpm. The instrumentation used to monitor speed was t
checked for calibration data and found acceptable. No inadequacies were identified.
8.
Test Loo Review A review was made of the Startup Engineers Shift Test Log for the period July 2-19, 1977.
No inadequacies were identified as to legging requirements of Test Instruction No.18. This item is resolved.
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Plant Tour
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The inspector toured selected areas of plant which included visual observation in the Reacter Building Control Room and New Fuel Storage b
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Area.
The inspector roted that the Reactor Building was being prepared for Hot Functional Testing.
0 :her comments en the condition of these areas are found in the details of this report.
With the exception of posting recuirements '
the New Fuel Storage Area, no items of noncompliance were identified.
10.
Exit Interview The inspector met with licensee representatives, denoted in paragraph 1, at tne conclusion of inspection on July 22 and July 28, 1977.
The inspector summarized the scope of inspecticn and the findings of the inspection as described in paragraphs 2 through 9.
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