ML19323B858
| ML19323B858 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 01/10/1979 |
| From: | Case E Office of Nuclear Reactor Regulation |
| To: | Boyd R, Deyoung R, Mattson R Office of Nuclear Reactor Regulation |
| References | |
| TASK-TF, TASK-TMR NUDOCS 8005140353 | |
| Download: ML19323B858 (2) | |
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EGCase hTRussell DFRoss Fliebdon DGEisenhut NRC PDR FSchroeder D!!Crutchfield DPJ1u11er
!!BAycock NRR A/Ds
'NRR B/Cs January 10, 1979 i
i ME!' ORA'iDl0 FOR Roger S. Boyd, Director, DP!i Richard C. DeYoung, Director, DSE Roger J. ?bttson, Director, DSS Victor Stello, Jr., Director, DOR FRO:*:
Edson G. Case. Chairman Technical Activities Steering Contittee i
SUEJECT:
f SUlNARY OF TECHNICAL ACTIVITIES STEERI:iG C0!?iliTEE MEETINGS NL"mERS 12 A'iD 13, NOVDSER 2 AND 13,1978 i
l i
l At Fleeting No. 12 on Novecher 2, 1975, the Steering Comnittee con-sidered a proposal by its Advisory Group for the definition of an
" Unresolved Safety Issue' for use in identifying which issues in NRR's generic issues progras qualify for reporting to Congress in accordance with Section 210 of the Energy Reorganization Act of 1974, as anended.
definition for trial use by the Advisory Group:The Steering Co "An Unresolved Safety Issue is a catter affecting several s
nuclear power plants for which it is likely that actions i
I may be needed to (1) compensate for a possible major reduc-
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tion in the degree of protection of the public health and safety. or (2) provide a potentially significant decrease in risk to the public' health and safety, when compared to that expected of plants currently being licensed for con struction or operation. ~
Following ?!ceting No.12, the Advisory Group utili::ed the definition l
agreed to by the Steering Cocmittee to perform a systecatic review t
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- lm Roger S. Eoyd Richard C. DeYoung January 10, 1979 Roger J. Mattson Victor Stello, Jr.
I of the issues in the NRR program. The Advisory Group's recommendations regarding which issues qualify as " Unresolved Safety Issues' were pro-vided to the Stocring Comittee in a memorandum dated November 9,1976.
A description of the review process utilized by the Advisory Group was also provided in that memorandum. 'Ihe Steering Committee considered these recomendations of the Advisory Group at Meeting No.13 on November 13, 1976.
As a result of the Steering Co=mittee's deliberations at f4eeting No. 13, the following issues were selected as " Unresolved Safety Issues.'
UNRESOLVED SAFETY ISSUES _
1.
h'ater llacner (A-1) 2.
Asymetric Blowdown Loads on the Reactor Coolant System (A-2) 3.
Pressurized Water Reactor Steam Generator Tube Integrity (A-3,
'A-4, A-5) 4 B1m Mark I and Mark II Pressure Suppression Containments (A-6. A-7,
. ' A-S. A-39) 5.
Anticipated Transients Without Scrar. (A-9) 6 B'in No::le Cracking (A-10) 7.
Reactor Vessel Fracture Toughness (A-11)
E.
Qualification of Class IL Safety-Pelated Electrical Equipment (A-24) 9.
Reactor Vessel Pressure Transient Protection (A-26)
- 10. Residual lient Removal Requirer.ents (A-31)
- 11. Seismic Design Criteria (A-40)
- 12. Pipe Cracks in Boiling ifater Reactors (A-42)
- 13. Emergency Sur:p Reliability (A-45)
- 14. Station Blackout (A-44)
The Advisory Group was directed to prepare a staff paper proposing these issues to the Commission.
In addition, the staff paper was to include a description of the selection process used by the Steering Co:r.ittee and \\
a draft Annual Report section describing the progress on each issue.
Od#af Srp:sg gy E. G. Can Edson G. Case, Chairman Technical Activities Steering Comittee
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