ML17199G578
| ML17199G578 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 05/08/1987 |
| From: | Muller D Office of Nuclear Reactor Regulation |
| To: | Thomas C Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8705110305 | |
| Download: ML17199G578 (3) | |
Text
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Docket No.*50~249,. '
MEMORANDUM FOR:.
C. Tho~as, Di rector
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Integrated.Safety Assessment ProJect Directorate
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FROM:
Daniel R. Muller, O.irector Project Di recto rate* II I-2 *
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SUBJECT:
- ~DRESDEN '.NUCLEAR _POWER. STATION, UN IT 2 (DRESDEN' 2)
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- 'SYSTEMAfIC EVALUATION~ PROGRAM (SEP).
The "commonweal th Edi son Co'. (CE Co).'.ha~- ~opera.ted Dr~sden 2 s i nee *December.22,
.1969 on Provisfonal Operatfog {t~ense *oRR-19. *.CECo applied for a full term operatin'g 1 i_cense on. November..".15, 19?.2.
- The SEP was initiated.by the NRC in 1977. '.This*evaluation was.largely comp.lete'd when the Integrated Plant. Safety Assessment Report (IPSAR) was iSsued "in Fe,bruary 1983.
- supplement 1 to the IPSAR has.'been in preparation since.t.hat~*time. *. Enclosure 1.~o t~i'.s memo provides the current ~tat~s of the IPSAR Supplement 1.
Pleas,e provide schedul'es.for those items.'to be reviewed in the: integrated Safety Assessment Project Directorate, (ISAP)' an'd indicate those items which will not be reviewed in ISAP~. *I wo*u*ld appreci~te a r,esponse. by May 13, 1987.
Our.go~l is to complete* the. IPSAR Supplement 1 by December 1987, and the. full term license *early in. 1988.
. *orlgi.nal s.i gned PY/
Daniel, R. Mul.ler,- Director
.. Proje~f Directorate III-2 Divisipn df Reactor Projects - 1II,.IV, V, and Special* Project~ *
Enclosure:
As stated
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.Enclosure 1 Suppl. 1 SEP Topic IPSAR Topic Title Section
'Status
- 1. II'.l-1 4.2.1 Radiography Requirements
...Cf Co 1 etter 4/20/87 Received
- 2.
IH-1 4.2.2 Fracture Toughness CECo letter 4/20/87 Received
- 3.
111-2 4.3.2 Ventilation Stack 2.Ll See 11/4/83 CECo letter
- 4.
III-2 4.3.3 Components Not Enclosed 2.1.2 Under NRC in Qualified Structures Review
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- 5.
II I-2 4.3.4 Roof Decks 2.1.3 Under NRC Review
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- 6.
III-2 4.3.5 Load Combinations See II I-7.B f'
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- 7.
I ll-4.A 4.5.1 Service Water System
..Not clear not in 4/22 8.
II I-4.A 4.5.2 Station Battery Systems Not clear t.-n
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not in 4/22
- 9.
III-4.A 4.5.3 Diesel Generator Not clear Ventilation not in 4/22
- 10. I II-4.A 4.5.4 Exterior Tanks Not clear not in 4/22
- 11. IIl-6 4.9.1 Piping Systems See Bulletin 79-14
- 12.
II~-6 4.9.2 Mechanical Equipment Under NRC Review
- 13. III-6 4.9.3 Qualification of Cable Owners Group Trays Program
- 14. 111-6 4.9.4 Ability of Safety GL..:87-02 Related Equipment &
Function
- 15. III-7.B 4.10 Design Code, Design Under NRC Criteria, etc.
- Review
- Suppl. 1
- SEP Topic IPSAR Topic Title Section Status
- 16. V-5 4.13.2 Seismic Qualification 2.7.2 Needs Inspection
- 17. V-10.B 4.15 Residual Heat Removal Under NRC System Reliability Review (App. R)
- 18. V-11.B 4.17 Residual Heat Removal Under NRC System Interlock Review (App. R)
Requirements
- 19. VI-4 4.18.2 Leakage Detections 2.8 Needs Inspection
- 20. VI-7.A.4 4.20 Core Spray Nozzle Part of A-16 Effectiveness I I
- 21. VI-7.C.1 4.21.5 Isolation of Class IE 2.9.3 Under NRC
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- sources from Non Class Review IE Loads
- 22. VI-10. B 4.23.1 Sharing of DC Systems 2.10 Under NRC Review
- 23. VII-1.A 4.24.1 Reactor Protection 2.11.1 Under NRC System Control System Review
- 24. VII-1.A 4.24.2 Process Computer 2.11.2 Under NRC Review
- 25. Vll-3 4.25.1 Procedures for Shutdown 4.0 Reg. II I from Outside Control audit needed Room
- 26. VIII-2 4.26.2 Prote~tion Trip 4.0 Inspection needed
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- 28. VIII-4 Electrical Penetrations
. F CECo
~evaluating