ML20082B121
| ML20082B121 | |
| Person / Time | |
|---|---|
| Site: | Seabrook |
| Issue date: | 08/02/1983 |
| From: | PUBLIC SERVICE CO. OF NEW HAMPSHIRE |
| To: | |
| Shared Package | |
| ML20079F081 | List: |
| References | |
| FOIA-83-388 NUDOCS 8311210008 | |
| Download: ML20082B121 (7) | |
Text
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FPm Seiten k m
SB 1 & 2 Q[
b ER-OLS 1
TABLE 7.4-6 ESTIMATES OF EVACUATION CLEAR TIMES (HOURS / MINUTES)
Off Season Sumer Weekday Weekend Zones Fair Weather Fair Weather
- 1. Sectors 1-4(*)
2/00 4/30 (10 miles)
- 2. Sectors 5-6(b) 2/40 3/45 (2 miles)
- 3. Sectors 7-10 3/00 3/50 (10 miles)
- 4. Sectors 11-12 3/10 3/45 (10 miles)
- 5. Sectors 13-16 3/00 3/40 (10 miles)
(*) Sixteen 22 0 sectors with sector 1 centered on the ' north counting clockwise.
0 0
(b)This is an average of the 180 N and 180 S, 2 mile radius data encompassing sectors 5 and 6.
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!g 450.2 Provide supporting documentation, in the form of appendices to ER-OL Chapter 7, that shows the derivations of the
!I Class 9 accident probabilities listed in Section 7.3 In addition to these derivations, provide any other 1.'
information that may be pertinent to verifying the class 9 J
accident probabilities.
RESPONSE
The supporting document: tic: fer the Cle:: 9 accident d
probabilities presented in Section 7.3 of the ER-OLS will be forwarded to the NRC Project Manager.
[i The Accident Evaluation Branch reviewer (Mohan Thadani) reconsnended that this information (approximately 500 pages of computer output) be included as an appendix to the ER-OLS. It is our opinion that the incorporation of t!'.is material as an appendix is not necessary. This matter has been brought to the attention of the NRC Project Manager and is pending resolution.
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t' 4a0.0 REACTOR SYSTEMS BRANCH t
4a0.1 Per Regulatory Guide 1.70, for the specific safety-related items
( 3. 5.1. 2) identified in Tables 3.2-1 and 3.2-2 provide eut following informa tion:
l'.
Reference drawing or piping and instrument diagram, where application, 2.
Identification of the missiles to be protected against, their source and the basis for selection, i
3.
Missile protection provided.
200.2 Soecify the available and recuired net cositive suction heac for (5.4.7.2) tne RHR pumes.
440.3 Discuss caterial ccmaatibility anc chemical effects as per (6.3.2.4)
Regulatory Guide 1.70, Revision 3.
~50.0 ACCIDENT EVALUATION BRANCH 253.1 As per Regulatory Suice 1.70, Revision 3, provide a descrintien of tne charcoal filter train, including design scecifications, flow parameters, and charcoal tyoe, weicht, and distribution;ME?A filter type and specifications; and specifications of any adcitier.a1 1
components.
The degree to which the recermendations of Regulatory Guide 1.52, " Design, Testing, and Maintenance Criteria for Postaccident Engineered-Safety-Feature Atacsphere Cleanup Systsm Air Fiitration and Adscr; tion Units of Light-Water-Cooled Nuclear ?c' er Plants,"
i are folicwed should be indicated and claimed filter ef ficier.cies listed.
Portior.s of this information that appear elsewhere in the FSAR may be referenced by section number.
450.2 Provide supporting documentation, in the form of appendices to ER-OL t
Cnapter 7, that shcws tne derivations of the Class 9 accident probabilities listed in Section 7.3.
In addition to these derivations, provide any other information that may be pertinent to verifying the Class 9 accident probabilities.
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