ML20235F317
| ML20235F317 | |
| Person / Time | |
|---|---|
| Issue date: | 09/21/1987 |
| From: | Randy Erickson Office of Nuclear Reactor Regulation |
| To: | Rubenstein L Office of Nuclear Reactor Regulation |
| References | |
| PROJECT-669A NUDOCS 8709290041 | |
| Download: ML20235F317 (3) | |
Text
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.EPRI.
Project No. 669 BEP 21 1987 l-MEMORANDUM FOR:
Lester S. Rubenstein, Director Standardization.and.Non-Power Reactor Project: Directorate Division of Reactor Projects III, IV, j
V and Special Projects
' Robert A. Erickson, Chief l
FROM: 1 Safeguards. Branch l
, Division'of Reactor Inspection &
Safeguards-i
SUBJECT:
PROPOSED DRAFT SAFETY EVALUATION REPORT ON CHAPTER 1 0F EPRI?S ADVANCED LWR UTILITY REQUIREMENT DOCUMENT Your memorandum of.Septembere14,.1987,; submitted for our review the Draft I:
Safety Evaluation Report'(DSER) concerning Chapter:1,'Overall Requirements,.
of EPRI's AdvanceduLWR Utility Requirements Document. We have no problems with the proposed DSER; however, enclosedLare some comments on Chapter 1 that.you taay wish to send-to'EPRI before they send us Chapters 6 'and 9 for i
review.
I
- Robert A. Erickson, Chief Safesuards. Branch Division of Reactor Inspection &
Safeguards
Enclosure:
As Stated-cc: Paul Leech' CONTACT B. T. Mendelaohn, NRR:RSGB ext. 29671 DISTRIBUTION
. Central Files PDR RSGB r/f RSGB s/f:
- Advanced Reactor Licensing-
' R.' A.Erickson B.T.Mendelsohn 1
0FC :NRR/RSGy
- NRR/RSGB
- NRR/
B
.... :...g f NAME : BMeh#..'csohn: RJDube
- RAEr son:
D_ATF: 9/)I/87
- 9/1,j/87
- 9/'7)/87 l'
0FFICIAL RECORD COPY 8709290041 870921 PDR PRDJ 669A PDR L
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UNITED STATES
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1j WASHINGTON, D. C. 20555 S,
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ST P 2 1 Igg, Project No. 669 MEMORANDUM FOR:
Lester S. Rubenstein, Director Standardization and Non-Power Reactor Project Directorate Division of Reactor Projects III, IV, V and Special Projects FROM:
Robert A. Erichson, Chief Safeguards Branch Division of Reactor Inspection &
Safeguards
SUBJECT:
PROPOSED DRAFT SAFETY EVALUATION REPORT ON CHAPTER 1 0F EPRI'S ADVANCED LWR UTILITY REQUIREMENT DOCUMENT Your memorandum of September 14, 1987, submitted for our review the Draft Safety Evaluation Report (DSER) concerning Chapter 1, Overall Requirements, q
of EPRI's Advanced LWR Utility Requirements Document.
We have no problems l
with the proposed DSER; however, enclosed are some comments on Chapter 1
{
that you may wish to send to EPRI before they send us Chapters 6 and 9 for i
review.
I
\\
/
~
l Ro ert A.
rf'ckson, Chief feguards Branch Division of Reactor Inspection &
Safeguards
Enclosure:
As Stated cc:
Paul Leech CONTACT B. T. Mendelsohn, NRR:RSGB ext. 29671
Lester S. Rubenstein, Enclosure EP22 g l
COMMENTS ON EPRI CHAPTER 1 1
l h
Page r
3 i
1-8 "The expected frequency of occurrence for higher off-site dose shall be less than once per million reactor years, considering both intern 81 and external events." Table 3-5, Man-Made Hazards j
in ALWR Design, includes sabotage.
The frequency of sabotage i
events is uncertain.
However, section 3.3 separates safety analysis events from man made hazards. Whether or not the freguency requirement is meant to include sabotage could'be clarified, particularly in light of the Severe Accident Policy Statement reference to reducing risks of sabotage.
2-21 Spatial separation of systems and equipment is required to be considered for seismic, fire, pipe rupture, and flooding events, but not for sabotage. Spatial separation of; trains is one technique being considered by NSSS vendors:to reduce risks of sabotage.
8-29 Section8.4.A.1specifiespersonnelaccessidrtal(PAP) criteria desired by the utilities.
Further discussion of these in Chapter 9 is desirable to assure that these criteria would not lead to any conflict with good security practice or NRC requirements.
8-51 Table 8-6 includes verification of security locks as one of the tasks which shall be considered for robotic application. More information on this could be necessary to determine if the application would represent good security practice.
Would the robot design requirement include the ability to check for tampering?
B-37 Table B-1 includes RG 1.17, June 1973, under current NRC criteria for design of advanced LWR.
Although this is still on the books, it is obsolete and need not be referenced.
B-49 Table B-1 should replace item 646, RG SG 302-4, with RG 5.65, issued Sept. 1986.
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