IR 05000320/1978030
| ML19224A280 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 10/19/1978 |
| From: | Haverkamp D, Kehoe D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19224A279 | List: |
| References | |
| TASK-TF, TASK-TMR 50-320-78-30, NUDOCS 7812010338 | |
| Download: ML19224A280 (5) | |
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U.S. NUCLEAR REGULATORY COMMISSION
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OFFICE OF INSPECTION AND ENFORCEMENT Region I Re:: ort No.
50-320/78-30_
Docket No.
50-320 License No.
DPR-73 Priority
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Category B2 Licensee:
Metropolitan Edison Company P. O. Box 542 Reading, Pennsylvania 19603 Facility Name:
Three Mile Island Nuclear Station, Unit 2 Inspection at:
Middletown, Pennsylvania Inspection conducted October 4-6, 1978
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Inspectors:
date si'gned
.'.Hederkaf/,$ReactorInspector JOfl0 7f N
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t date' signed D7 V. Kehoe, Reactor Inspector date signed
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/4 - /9 - 78 Approved by:
date signed R. Ke d Chie,
actor Projects
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Sectio. o. 1,
'45 Branch Insoection Summary:
Inspection on October 4-6,1978 (Recort No. 50-320/78-30)
Areas Inspected:
Routine, unannounced inspection by regional based inspectors of Technical Specification compliance during startup phase operation, including limiting conditions for operation and administrative controls for design changes.
The inspection involved 22 inspector-hours onsite by one NRC regional based inspector and one inspector-trainee.
Results: No items of noncompliance were identified.
481201053I Region I Form 12 I
(Rev. April 77)
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DETAILS 1.
Persons Contacted
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Metropolitan Edison Company
- Mr. M. Bezilla, Unit 2 PORC Secretary Mr. J. Floyd, Unit 2 Supervisor of Operations Mr. J. Hilbish, Station Lead Nuclea" Engineer Mr. F. Scheimann, Jr., Shif t Forect
- Mr. J. Seelinger, Unit 2 Superintendent-Technical Support Mr. R. Sieglitz, Unit 2 Maintenance Engineer Mr. W. Zewe, Shift Supervisor General Public Utilities Service Corporation Mr. R. Toole, Test Superintendent The inspector also interviewed several other licensee and contractor employees during the inspection. They included control room operators and engineering and maintenance staff personnel.
- denotes those present at the exit interview on October 6,1978.
2.
Review of Limiting Conditions for Operation The inspector observed control board equipment start switches, electrical power supply breaker positions and process instrucen-tation menitoring operations on October 5 and 6,1978.
The inspector reviewed records of previous reactor operations during September 25 - October 5,1978.
7%e following logs and records were reviewed:
Shift Foreman Log
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Control Room Log Book
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Completed Surveillance Procedures 2301-S1, " Shift and
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Cdily Checks", Revision 10.
The observations and records review were conducted to verify that reactor operations were in conformance with the following Technical Specification limiting conditions for operation:
3.1.1.4 - RCS lowest loop Tavg
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3.1.2.2 - boron injection flow paths operating
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3.1.2.4 - makeup pumps operable
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3.1.2.9.a - reclaimed boric acid tank volume and
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boron concentration 3.1.2.9.b - borated water storage tank volume,
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baron concentration and temperature 3.1.3.1 - control rods operable and correctly positioned
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with respect to group average height 3.1.3.2 - axial power shaping rods operable and
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correctly positioned 3.1.3.3 - safety, regulating and APS rod reed switch PI
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channels and pulse stepping PI channels operable 3.1.3.6 - safety rods fully withdrawn
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3.1.3.7 - regulating rod groups limited in insertion
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per Figure 3.1-2 3.1.3.7 - control rods programmed to operate in core
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position and rod group per Figure 3.1-8 3.2.1 - axial pcwer imbalance within limits of Figure
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3.2-1
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3.2.5. - RCS pressure and hot log temperatures
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3.4.1 - RC loops and pumps operable
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3.4.4 - p essurizer operable
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3.4.5 - steam generators operable
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3. 4. 6. 2 - RCS l eakage
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3.4.7 - RCS chemistry
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3.5.1 - core flood tank volume, baron cor. centration
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and nitrogen cover pressure 3.6.1.4 - primary containment internal pressure
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2.256
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3.6.1.5 - primary containment average air temperature
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3.6.1.7 - containment purge supply and exhaust valves closed
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3.6.2.2 - spray additive tanks volume and NaOH concentration
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3.6.2.3 - containment cooling subsystems operable
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3.6.4.2 - containment hydrogen recombiner operable
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3.6.4.2 - containment hydrogen purge cleanup
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system operable 3.7.1.3 - condensate storage tanks volume
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3.7.5.1 - ultimate heat sink (river) water level
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and temperature.
Findings were acceptable, except as noted below.
Technical Specification 3.6.2.2 states that the spray additive
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(Na OH) tank volume shall be maintained at 13,275-14, 100 gallons, which corresponds to approximately 46.6 - 49.6 feet tank height.
The inspector determined that the actual tank volume was within limits and the level alarm annuciator setpoints were correct.
However, incorrect level alarm values were posted on the annunciator alarm window and were included in the alarm response procedure.
In addition, an incorrect tank level (feet) to volume (gallons) conversion factor was listed in the control room tank curve book.
This item is unresolved pending correction of these specific items and generic licensee review of other alarm setpoints to determine proper posting and incorporation in alarm response procedures. (320/78-30-01)
3.
Administrative Controls For Design Changes The inspector reviewed selected desian changes approved since issuance of the operating license, including those requested by contractor organizations. The design changcs reviewed are listed below:
TMI - 2 Change / Modifications 2-0013 2-0076 2-0116 2-0014 2-0077 2-0119 2-0015 2-0080 2-0120 2-0031 2-0084 2-0125
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2-0060-2-0099 2-0134 2-0068 2-0100 2-0136 2-0074 2-0103 2-0142 2-0075 2.257 2-0105 i
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Burns and Roe Field Ouestionnaires/ Engineering Change Memos 2441/S-8770 2529/S-5934 2442/S-5828 2530/S-5933 2452/S-5831 2532/S-5939 2453/S-5830 2558/S-5920 2457/S-5851 2562/S-5970 2460/S-5832 2569/S-5976 2461/S-5833 2573/S-5990 2477/S-5847 2583/S-5999 2483/S-5866 2649/S-9085 2489/S-5887 The design changes were reviewed to verify that they were approved and evaluated as required by 10 CFR 50.59, applicable Technical Specifications, and the following administrative procedures:
Generation Procedure 1003, " Control of Design Changes / Modifications,
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" Revision 3, with Change Memo #3 TMI Station Administrative Procedure 1021, " Plant Modifications",
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with TCN 2-78-648 Burns and Roe, Inc. TMI-2 Project Procedure PP-86, " Field Questionnaire
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and Field Change Request, Revision 7.
No items of noncompliance were identified.
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Unresolved Items Unresolved items are matters about which more information is required in order to ascertain whether they are acceptable items, items of noncompliance or deviations.
An unresolved item disclosed during the inspection is discussed in Paragraph 2.
5.
Exit Interview The inspector met with licensee repres.entatives (denoted in Paragraph 1) at the conclusion of the inspection on October 6, 1978.
The inspector summarized the purpose and scope of the inspection and the findings.
23. 5$365