ML20202F942
| ML20202F942 | |
| Person / Time | |
|---|---|
| Issue date: | 12/04/1997 |
| From: | Stolz J NRC (Affiliation Not Assigned) |
| To: | Smith N MPR ASSOCIATES, INC., SEISMIC QUALIFICATION UTILITY GROUP |
| Shared Package | |
| ML20202F947 | List: |
| References | |
| REF-GTECI-A-46, REF-GTECI-SC, TASK-A-46, TASK-OR TAC-M93624, NUDOCS 9712090266 | |
| Download: ML20202F942 (4) | |
Text
_ _ _ _ _ _ _ ..
'1 e
fv?:%
.p'- k UNITED STATES -
'g
[ .
- NUCLEAR REGULATORY COMMISSION
- WASHINGTON, o.C. spee6 ecot O,,. --
t ......
December 4,1997 Mr. Neil P. Smith, Chairman -
Seismic Qualificrtion Utility Group clo MPR Associates,Inc.
. 320 King Street Alexandria, VA 22314
SUBJECT:
SUPPLEMENTAL SAFETY EVALUATION REPORT No. 3 (SSER NO. 3) ON THE
- REVIEW OF REVISION 3 TO THE GENERIC IMPLEMENTATION PROCEDURE
. FOR SEISMIC VERIFICATION OF NUCLEAR POWER PLANT EQUIPMENT, UPDATED MAY 16,1997 (GIP-3) (TAC NO. M93624)
Dear Mr. Smith:
Enclosed is the Supplemental Safety Evaluation Report No. 3 (SSER No. 3) that provides the staffs evaluation of the Generic Implementation Procedure, Revision 3 (GIP-3), updated
.May 16,' 1997, submitted by the Seismic Qualification Utility Group (SQUG) for seismic verification of nuclear power plant equipment.
The staff finds that the changes in the restrictions on the use of the in-cabinet ampd.ication factor, corrections in equations for determining allowable anchorage capacity for horin .tal tanks and heat exchangers, and the editorial and typographical changes are acceptable. Th etaff also finds ihat the changes in anchorage criteria as updated in GIP-3, dated May 16,1997,' are -
acceptable as delineated in the attached SSER No. 3.
In spite of the conclusions reached in this very focused review of the GlP-3 revision, the staff has identified, during its review of licensees' documentations of A-46 implementations, certain areas which cou d result in misapplication of GIP-2 due to lack of specificity and the potential for misinterpretation of GIP-2 provisions relating to these areas. These issues are being resolved
.with SQUG separately. The staffs position on these issues is discussed in the response to SQUG dated December 2,1997, and is applicable to GIP-3 as well as GIP-2. Consequently, the
> staff recommends that future revision of the GIP should include, as applicable, any necessary -
. clarifications to the provisions, to reflect the staffs position, in areas identified as ambiguous or susceptible to misinterpretation by GIP users, go) . ) S3 f
. ~
wCOM p g (% lc E MiUl b-,.ym* ggpy' pppqqsyg WoM 9712090266 971204 PDR- REV9P EROSeUO l PDR -
Neil P. Smith if you have any questions regard.ng this matter, please contact Mr. Dan Dorman at (301) 415 1429.
Sincerely, A4d. CD-
- John F. Stolz, Lead Project Director Project Directorate 1-2 Division of Reactor Projects - 1/II ONice of Nuclear Reactor Regulation
Enclosure:
GlP-3 Supplemental Safety Evaluation Report cc w/ enc: Mr. R. Kassawara, EPRI Program Manager 3412 Hillview Avenue P.O. Box 10412 Palo Alto, CA 94304
~
[ '
Decemaber 4, 1997 9
- Jeil P. Smith 2-t if you have any questkms regarding this matter, pierse contact Mr. Den Domian at (301)415 1429. .
Sincerely, Original Signed by: Donald S. Brinkman/'
for John F. Stolz, Lead Project Director Project Directorate 12 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation
Enclosure:
GIP 3 Supplemental
- Safety Evaluation Report ec w/ene
- Mr. R. Kassawara, EPRI Proglam Manager 3412 Hillview Avenue P.O. Box 10412 Palo Alto, CA 94304 QlSTRIBLI1QN-
' Central FD BBoger RWessman GBagchi CHohl, RGN I PUBLIC SLittle DDorman OGC PD12 R/i JStolz PYChen ACRS DOCUMENT NAME: G:t DORMAN\SQUG2.LTR To receive a copy of this document, Indicate in the box: 'C" = Copy Wthout attachment / enclosure *E" = Copy with attichment/ enclosure "N" = No copy orrict rairoi1 g4 Ie uiroi 1 ; pn IE ciroi r N6 1 1 I mAug oponMAN Cf /wf J deliitt @
- JSTOLZ %-
DAtt 17/ y /97 L 12/44/97 12/ */ /97 12/ /97 12/ /97 Of ficial Record Copy n
n; -
t
- s
- 4. -
-- ,__- -__~_ - - ._. . .. . _ . _ .- -
4 Dee.enaber 4, 1997 p.. l I
Neil P. Smith 2 f
if you have any questions regarding this matter, please contact Mr. Den Dorman at (301) 415 1429.
Sincerely, Original Signed by: Donald S. Brinkman/
for John F. Stolz, Lead Project Director Project Directorate i 2 Division of Reactor Prcjocts t/ll Office of Nuclear Reactor Regulation
Enclosure:
GlP 3 Supplemental Safety Evaluation Report cc w/ enc: Mr. R. Kassawara, EPRI Program Manager 3412 Hillview Avenue P.O. Box 10412 Palo Alto, CA 94304 DISTRIBUTION:
Central File BBoger RWessman GBagchl CHohl, RGN I PUBLIC ELittle DDorman OGC PD12 R/F JStolz PYChen ACRS DOCUMENT NAME: GA DORMAN\SQUG2.LTR To receive a copy of this document, indicate in the box: "C" = Copy without attachment / enclosure "E" = C,py with attachment / enclosure *N" = No copy Trier pa: Poi i o ,1e tairoi i ; pn IE oiroi.2 t#; I I I saw nocama C/ ,co< ; evittir #- niot? %-
Davr 12/ 4 /97 L 12/Af /97 12/ Y /97 12/ /97 12/ /97 Official Record Copy
<