IR 05000387/1979024
| ML17138A818 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 08/07/1979 |
| From: | Caphton D, Nicholas H NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML17138A817 | List: |
| References | |
| 50-387-79-24, NUDOCS 7910020411 | |
| Download: ML17138A818 (8) | |
Text
U.S.
NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT Region I Report No. 50-387/79-24 Docket No. 50-387 License No.
CPPR-101 Priority:
Licensee:
Pennsylvania Power and Light Company 2 North Ninth Street Allentown, Pennsylvania 18101 Facility Name:
Susquehanna Steam Electric Station, Unit
Inspection at:
Berwick, Pennsylvania Category:
B ate signed Inspection conducted:
July 10-12, 1979 Inspectors:
H. H. Nicholas, Reactor Inspector C. K. Sweinhart Reactor Ins ector CO-OP date signed Approved by:
D. L. Cap t n, C )ef, Nuc ear Support Section No. 1, RO&NS Branch Ins ection Summar:
F 77 ate soigne Ins ection on Jul 10-12, 1979 Re ort No. 50-387 79-24
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inspector of the preoperational test program including test program review requirements, test procedures and test sequencing; cooling water systems; tours of the facility; and followup on previous inspection items.
The inspection involved 23.0 inspector hours on site by one NRC regional based inspector.
Results:
No items of noncompliance were identifie DETAILS 1.
Persons Contacted Penns lvania Power and Li ht Com an Hr. J. Bradford, Quality Supervisor Mr. G. Burvis, NQA Engineer Mr. R.
Byram, Supervisor of Maintenance Mr. P. Capotosto, NQA Engineer
- Mr. T. Clymer, Senior NQA Analyst Mr. J.
Graham, Asst. Superintendent of Plant
- Mr. J.
Green, Resident NQA Engineer
- Mr. E. Gorski, Senior Nuclear Quality Specialist Mr. G. Kuczynski, Starting and Testing Field Engineer Mr. J.
Hahoney, Starting and Testing Field Engineer Hr. L. O'eil, Test Supervisor Hr.
R. Mood, Civil Construction Engineer Bechtel Power Cor oration Mr. G. Smith, ISG Supervisor U.
S. Nuclear Re ulator Commission
- Hr. R. Gallo, Resident Reactor Inspector The inspector also interviewed other licensee personnel during the course of the inspection.
- Denotes those present at the exit interview.
2.
Status of Previous Ins ection Items (Closed)
Inspector Followup Item (387/79-08-01)
Incorporation of test personnel qualifications into administrative manual and appointment of personnel to positions.
The staffing of these positions and the incorporation of qualifications into the administrative manual has been completed by the licensee.
The inspector had no further questions at this time and this item is close (Closed)
Inspector Followup Item (387/79-08-02)
Ensur'e that assigned members of test staff have completed required adminis-trative manual training.
To date, all test staff members have completed this training.
The licensee's representative stated that when new members join the test staff, they will receive this training as required by the training/reading list prior to active involvement in preoperational testing.
The inspector will follow up on this item during subsequent inspections of test program implementation.
The inspector had no further questions at this time, and this item is closed.
3.
Prep erational Test Pro ram a.
Test Pro ram Review Re uirements Discussion:
The inspector met with the integrated startup group (ISG)
supervisor and concluded discussions in the following areas of test program requirements:
Test program; Test organization; Test program administration; Document control; Design changes and modifications; Plant and Preventive Maintenance; Equipment protection and cleanliness; Test and measuring equipment; and Training.
References:
Final Sa'fety Analysis Report, Chapter 14; Regulatory Guide 1.68, Initial Test Programs for l<ater Cooled Nuclear Power Plants; Startup Administrative Manual; and Startup Technical Manual.
Findings:
As a result of discussions with the -integrated startup group supervisor and his staff, and a review of the
referenced documents, no discrepancies were noted, and the inspector had no further questions at this time.
A further review of documents and records, and discussions with the licensee's representatives will continue during test program implementation.
b.
Areas of Concern Durin Preo erational Testin Discussion:
The following areas and items were discussed with the ISG supervisor:
Shared structures, systems and components of units 1 and 2; Integrated flush of reactor pressure vessel and associated systems; Hydrostatic test of reactor pressure vessel and associated systems; Critical path for test scheduling, testing and test sequencing; Leak rate testing types, status and procedures; Snubbers, spring hangers, pipe supports and restraints; Freeze protection; and The NRC inspectors'oll in test witnessing and subsequent inspections.
References:
Regulatory Guide 1.68, Initial Test Programs for Water Cooled Nuclear Power Plants; Regulatory Guide 1.68.1, Preoperational and Initial Startup Testing of Feedwatet and Condensate Systems for Boiling Water Reactor Power Plants; Startup Technical Manual Final Safety Analysis Report, Chapter 14; Startup Administrative Manual; and Diagrams, Prints and Procedures Findings:
No concerns were identified as a result of the discussions with the ISG supervisor and the review of the referenced
documents except in the area of freeze protection.
Freeze protection has not been addressed generically in adminis-trative, technical, or maintenance procedures such that all situations would be handled.
During further discussions with the ISG supervisor, it appears generic freeze protection procedural considerations need resolution.
This item will be inspected during a
subsequent inspection and is designated as an item for inspector follow-up (387/79-24-01).
c.
Test Procedures and Test Se uencin Discussion:
The inspector met with the startup and test coordinator and discussed the status of procedures, their review and approval, and test sequencing.
The following draft copies of procedures were received for NRC inspection:
P79.2A, Revision
Process 5 Effluent Radiological Monitoring System P79.2 B; Revision
Process 5 Effluent Radiological Monitoring System P79.2C, Revision
Process 5 Effluent Radiological Monitoring System P79.2D, Revision
Process 5 Effluent Radiological Monitoting System P80.1, Revision
Reactor Non-Nuclear Instrumentation A46.1, Revision
Extraction Steam System A91.1A, Revision
Plant Annunciators TP3.26, Revision
Integrated Flush FCI-M169, Revision B
Reactor Vessel and Associated Piping Hydro
& Sampling 5 Sampling 5 Sampling 5 Sampling static Test
Findings:
~
Based upon discussions with the startup and test coordinator, review of the licensee's procedure status, availability and-timeliness of procedures for inspection, and the inspection of the licensee's procedure review cycle and sequencing of tests, the inspector had no further questions at this time.
4.
Coolin Water S stems Discussions:
The inspector interviewed licensee's representatives in the startup group, startup and testing, quality assurance, and the ISG supervisor and held discussions on the following:
River Intake Structure; River Water Makeup System; Cooling"Towers and Basins; Circulating Water and Service Water Pump House; Circulating Water System; Service Water System; Spray Retention Pond; ESSW Pump House; RHR Service Water System; Emergency Service Water System; and Raw Water Treatment System.
References:
Final Safety Analysis Report; Startup Administrative Manual; Startup Technical Manual; System Description Manual; and Prints, Drawings and Diagrams.
Findings:
As a result of the inspections of systems, components, areas and structures, and review of referenced documents, no discrepancies were noted and the inspector had no further questions at this time.
A review of these systems, their procedures, completions and turnovers, will'ontinue during subsequent inspection.
Plant Tours The inspector made several tours of the facility including the following areas:
Turbine Building; Reactor Building; Containment; Control Structure; Control Room; E'mergency Shutdown Station Outside Control Room; River Intake Structure; Cooling Towers and Basins; Spray Pond and ESSW Pump House; and Circulating Water and Service Water Pump House.
The inspector observed work in progress, housekeeping, cleanliness, controls,-storage and protection of equipment, components, piping and systems.
No items of non-compliance were identified and no discrepancies were noted.
6.
Exit Interview At the conclusion of the site inspection on July 12, 1979, an exit meeting was conducted with the licensee's senior site representatives (denoted in Paragraph 1).
The findings were identified and previous inspection items were discusse '0