ML20058F406
| ML20058F406 | |
| Person / Time | |
|---|---|
| Issue date: | 07/22/1982 |
| From: | Ippolito T Office of Nuclear Reactor Regulation |
| To: | Lainas G Office of Nuclear Reactor Regulation |
| References | |
| REF-GTECI-A-03, REF-GTECI-A-04, REF-GTECI-A-05, REF-GTECI-SC, REF-GTECI-SG, TASK-A-03, TASK-A-04, TASK-A-05, TASK-OR NUDOCS 8207300471 | |
| Download: ML20058F406 (4) | |
Text
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J. as co, o,
UNITED STATES g-
,g NUCLEAR REGULATORY COMMISSION
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j WASHINGTON D. C. 20555
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JUL 2 21982 MEMORANDUM FOR:
Gus C. Lainas, Assistant Director for Safety Assessment Division of Licensing FROM:
Thomas A. Ippolito, Chief Operating Reactors Assessment Branch Division of Licensing
SUBJECT:
FORTHCOMING MEETING WITH STEAM GENERATOR OWNERS GROUP - PROPOSED STEAM GENERATOR GENERIC REQUIREMENTS Date & Time:
July 29,1982 10:30 a.m. - 5:00 p.m.
Location:
Phillips Building, P-ll8 Bethesda, MD Furpose:
To discuss the value/ impact assessment of the draft NRC report "NRC Requirements Concerning Steam Generator Tube Degradation and Rupture Events (Including resolution of USI's A-3, A-4, and A-5)"
in accordance with the attached agenda.
l Participants :
NRC D. Eisenhut, R. Mattson, S. Hanauer, R. Vollmer, R. Baer, R. Ramirez, G. Lainas, T. Ippolito, T. Marsh, J. Strosnider, J. Moorehouse(SAI).
SGOG A. Schmidt, L. White, P. Santoro, R. Acosta, R. McCredy, B. Snow, A. Curtis
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AIF A. Bivins EPRI S. Green Ut* f k
Thoma
. Ippolito, Chief Operating Reactors Assessment Branch g
Division of Licensing j
Attachment:
As Stated
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8207300471 020722 DRTOPRPEUTOGg
ATTACHMENT
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AGENDA 1
1.
Introduction II.
Proposed Licensee Requirements 1.
Steam Generator Integrity Prevention and Detection of Loose Parts or Foreign Objects Stabilization and Monitoring of Degraded Tubes
- Inservice Inspection Program
- Improved Eddy Current Techniques
- Primary to Secondary Leakage Secondary Water Chemistry Program
- Condenser Inservice Inspection Program Upper Inspection Ports 2.
Plant Systems Response
- Reactor Coolant System Pressure Control During A SGTR Safety Injection Signal Reset
- Containment Isolation and Reset 3.
Human Factors Consideration None 4.
Radiological Consequences
- Standard Technical Specification Limit for Coolant Iodine Activity 5.
Organizational Response None III. NRC Proposed Actions 1.
Steam Generator Integrity Steam Generator Tube Sleeves 2.
Plant Systens Response
- Steam Generator Overfill i
- PORV Operability Pressurized Thermal Shock Improved Accident Monitoring Reactor Vessel Inventory Measurement
3.
Human Factors Consideration Requirement on Reactor Coolant Pump Trip Rotary Switch Functional Identification Indicator Lights Burned Out Inconsistent Terminology Emergency Operation Procedures Improvement 4.
Radiological Consequences Reassessment of Radiological Consequences Following a Postulated Steam Generator Tube Rupture Event Reevaluation of SGTR Design Basis Event Secondary System Isolation Review of Ventilation Intakes Collection of Snow Samples 5.
Organizational Response Interactions with Regional Base Teams by the NRC Executive Team
- NRC Site Team Familiarization with NRC Response Plan
- Alternate Evacuation Routes and Sites Deescalation of Emergency Classification Offsite Dose Assessment f
I
l a
1 MEETING NOTICE DISTRIBUTION JUL 2 21982 Central Files NRC PDR Local PDR ORAB Reading NSIC OELD OISE ACRS (10)
D. Eisenhut T. Ippolito R. Mattson S. Hanauer R. Vollmer R. Baer R. Romirez G. Lainas T. Marsh J. Strosnider W. Johnston j
E. Jordan i
H. Thompson i
B. Grimes M. Hawkins K. Wichman R. Martin E. Murphy V. Benaroya P. Norian W. Mills Receptionist (Phillips Bldg.)
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