ML19329F596
| ML19329F596 | |
| Person / Time | |
|---|---|
| Site: | Midland |
| Issue date: | 07/18/1977 |
| From: | Howell S CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | Boyd R Office of Nuclear Reactor Regulation |
| References | |
| RTR-REGGD-01.001, RTR-REGGD-01.004, RTR-REGGD-01.007, RTR-REGGD-01.015, RTR-REGGD-01.025, RTR-REGGD-01.027, RTR-REGGD-01.042, RTR-REGGD-01.052, RTR-REGGD-01.059, RTR-REGGD-1.001 3986, NUDOCS 8007020749 | |
| Download: ML19329F596 (8) | |
Text
.
C0!1 sum 8FS 1 PD"IBf h QQ Stephen H. Howell Vice President 5lD
y General offices: 1945 West Pernali Road. Jackson, Michigan 49201
- Area Code 517 788-045 Q p^rr,
\\
July 18, 1977 7 h ('
y iV[.b
-d h
JUL23 M us. g j/lN F
/
Director of Huclear Reactor Regulation N/
Attn: fir Roger Boyd, Director T
,s9/
Q\\
Division of Project Ihnage=ent s
US Uuclear Regulatory Cor=ission Washington, DC 20555 MIDLAND PROJECT p m,,, # %-
,. s,,
DOCKET JOS 50-329, 50-330 y,g',
d~
, ' ~ "
MISCELLANEOUS CATEGORY EVALUATIOU OF REGULATORY GUIDE POSITIOUS
--...,, M Ny FILE: 0505 SERIAL:
3986
'd I /
Mr S A Varga's September 29, 1976 letter transmitted the UFC Staff evaluation of the Consumers Power Company position on Regulatory Guides 1.1, 1. 4, 1. 7,
1.15,1.25,1.27,1.h2, l.h9,1 52, and 1.59 relative to the Fidland Plant.
Subsequent to your review scme of our positions have changed, or require addi '
tional clarification due to reinterpretation of Regulator / Guide contents.
Also, ve vish to advise you of our intended action in those areas where the Staff's position is interpreted to be different from the Consumer's position. is a Suttar/ Status of each Regulatory Guide reviewed in the Struc-tural Engineering category. Attach ents 2 thru 6 provide additional discussion on individual Regulatory Guides.
Tne attached caterial is for infornation only since URC evaluation of the final
- Ildland Plant Regulatory Guide positions will be performed during review of the Final Safety Analysis Report which is scheduled for submittal on September 1,1977
<-(
t miQ SEH/jg
(
CC: CEMahaney, Lyncifcurg [2]
RLCastlederry, A2 [3]
THIS DOCUMENT CONTAINS P0OR QUAUTY PAGES 8007020 7
SUMMARY
STATUS OF MISCELLMIEOUS REGULATORY GUIDES Regulatory Guide Conment 1.1' NRC agrees with Midland Position 1.4 See Attachment 2 1.7 NRC agrees with Midland Position 1.13 See Attachment 3 1.25 See Attachment 3 1.27 See Attachment 4 1.42 NRC agrees with Midland Position 1.49 NRC agrees with Midland Position 1.52 See Attachment 5 1.59 See Attachment 6 i
l l
4.h egne te emose e he.m..
.ew,.
A
'o Regulatorv Guide 1.4
" Assumptions Used For Evaluating the Potential Radiological Consequences of a Loss-of-Coolant Accident For Pressurized Water Reactors" - (Revision 2, June 1974)
The NRC staff concurs 4th the Midland positions provided calculations utilize " semi-infinite cloud" assumptions. The applicant will comply and complete FSAR calculations using semi-infinite cloud assumptions given in the Regulatory Guide for both conservative and realistic analyse's-o e
O 1
L.
.n
" Fuel Storage Facility Design Basis" -
(Safety Guide 13, March 10, 1971)
" Assumptions Used For Evaluating the Potential Radiological Consequences of a Fuel Handling Accident in the Fuel Handling and Storage Facility For Boiling and Pressurized Water Reactors" - (Safety Guide 25, March 23, 1972)
.E The ilRC agrees with the Midland position provided the plant design includes charcoal adsorbers in the exhaust system for the spent fuel storage facility. The adsorbers are included in the exhaust of the spent Fuel Pool Area Ventilation system, therefore, the positions for Regulatory Guides 1.13 and 1.25 are considered resolved.
" Ultimate Heat Sink For Nuclear Power Plants" -
(Revision 1. March 1974)
The NRC has indicated two acceptable alternates to the applicant's position if the applicant's final analysis shows the peak pond temperature to be above the service water system design temperature. These two alternates are 1) verification of equipment performance at the peak temperature or
- 2) to implement a technical specification to limit power level when the ultimate heat sink reaches a predetermined temperature.
The applicant is now completing the final analysis on the ultimate heat sink performance and, although complete checking of the calculations remains to be done, the maximum peak-pond temperature obtained is 105.3F and exists for the relatively short period of approximately five hours.
Based on these results, which will be confirmed and reported in the FSAR, the applicant believes that neither of the above alternates proposed by the staff will be necessary.
1 I
p,
.~
^-
ttcchment 5
~
" Design, Testing and Maintenance Criteria for Atmospheric Cleanup System Air Filtration and Absorotion Units of Light-
- Water-Cooled Nuclear Power Plants" - (June 1973)
The NRC concurred with the Midland position except for the alternates proposed for Section C.2.a and C.3.J.
On these sections, the NRC staff believed sufficient justification for the applicants deviations had not been provided. The staff felt that demisters should be provided for the Emergency Fuel Handling Area Exhaust Units and that a single failure proof, low flow air bleed system, to inhibit adsorber fires, should be included.
In response to these concerns the following design features have been incorporated:
1)
C.2.a - Demisters are being provided for the spent fuel exhaust or as called by the NRC the Emergency Fuel Handling Area Exhaust Units.
2)
C.3.j - Detailed calculations have been performed to determine the maximum rate of temperature rise for no air flow through a charcoal bed loaded to its design level. The results of these calculations show that the maximum temperature rise possible is 0.02F/hr.
Although this temperature rise is considered insignificant, permanently installed spray piping, which can be manually connected to local fire hoses should this ever be necessary, will be provided inside the air filtration unit housing. The Midland project therefore complies with the requirement of Section C.3.j.
A further point of clarification is also needed in regards to position
?
C.S.C.
The carbon adsorber will be tested in accordance with Section 12 of ANSI N510.
O
-~
{.,,
Attrch: nt 6 Regulatory Guide 1.59
" Design Basis Floods for Nuclear Power Plants"-
(August 1973 The NRC is in agreement with the Midland position provided the Technical Specification (Chapter 16 of the FSAR) reference " acceptable emergency procedures that assure acceptable sandbagging procedures for flood protection".
The NRC also requires that the applicant demonstrate in the (FSAR) that erosion of the Tittabawassee River bank adjacent to safety-related facilities will not endanger systems necessary to shut down and cool down the plant.
The sandbagging technical specification will be provided in the FSAR. The protection from erosion of systems necessary to shut down and cool down,the plant will also be demonstrated in the FSAR.
^
U.S. NL,CLEA A fiEGULA7CnY COMMISstCN 3CCitE' M
' NRC'acPM 195 cr.7s)
E M
336
~
NRC DISTR'IBUT!CN pen PA..s' 50 DCCKET MATERIAL FROM:
CATE CP OCCUMENT h "Mr. Roger Boyd
, Jackson, Mich.
49201 Consumers Power C 7-18 77 l
- T*"'C*
S. H. Howell 7 25-77 4
z,g.7sn
?
ance iNeurmonu Nuussa en copies macsivso 26moiNAL 2"use: Assinise Ceepv
/ d/6AldD escLosuas ATTACMENT 1 is entitled Summary of each
- sscascioN Ltr trans the following:
IP Reg Guide reviewed in the misc category eval ff ou ej 2Q-7d %
group & ATTACHMENfS 2-6 provide addl discussidn f
on individual Reg Guides.....
10P
'~,
7 i
(1 cy encl rec' d) 8e f _'
f
- hc; t
?LANT NAME: Midland 1 c 2 e
i
?HL 7 25-77 cArrev FOR ACTION /INFORMATION ENVIRtIN>5NTAL i
i/ ASSTCNED AD?
(1),)I l'
ASSIGNED AD:
V. MCORE (LTR)
/s uniNcu rRTE7?
G [2 l V46#
l R GCE CHIEF?
/l_
?RCJECT M_ GAGER: &'i' l
i PROM CT MANAGER:
I 1 Ml!4 I
LICENSING ASSISTANT:
I
/
LICENSING ASSISTAN3:
E t
I i I I
- 3. uARLIs3 INTERNAL DISTRIBUT!CN l
C/_i ere rTrec )
1 I SYSTFM3 SAFETY I i PLANT SYSTEMS I SITE SA.rETf &
I
'/ t roc ano 1 1METNEMAN l/l TEDESCO (Ldy) iENVIRON ANALYSIS t
'/i 7 a, r, {M i iScuROEDER I/l3ENAROYA l DENTON & MULLER I
- ft ner n (L&)
I t/irATNAe.
I i
co'" curter n i
iccSST K & stare ENGINEERING VIIPPOLITO I
I i
I uinste, nr cu-l/l. ROSA I
DIVIRO TECH.
I fa vvoc (Lh.).
l/l ?OcNAK i l i I EPSST i
[_,i c a er '
e'l/I SIu. JELL 1 OPE?.ATING REACTORS I
i 3ALLAPI)
I lurvn f/l DArir,TcKT 4
STELLO I
I YOUNC3LCOD i
i i i
i l Tcr?r.nf*
I i
i ieenne-usyinev NT I oricano cATErr I i CHAO l _ _ _ _..
I I evnvuct.*
If ROSS [LN) l I 3AER I
~ ~ ~ ~ ~ ~ ~ '
I I 3UT'LER I/
GAMMILL (I) i/l 3 car 7TNS
'/I NOVAK\\
I/Iunric~N If ROSZTUC2Y l l GR ES I
l I
I I vrt T I/ CHECK l i I
I SITS ANALYSIS I /i urt **M S I i l l I/I VOLLMER (l/.A i
I I CY l iATLI I I
'/l 3UNCH I
6 l i l SALTZv_AN I i
/t J. CCLLINS I
' I I
Io"*? ERG 1 I l/l KREGER I
EXTERNAL CISTRIBUTICN CONTROL NUM BER i.
'fi L?DR? /*f/DJ AD/). M/t*s)J l
1
'l I
-7920buutu ' f-
- 1. REC IV (J. MANCHETT)i I l
g
'/ 15 CYS ACRS SEIT CAT GCRY T l
l
- M s
b