ML20126B180
| ML20126B180 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 12/17/1992 |
| From: | William Cahill, John Marshall TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| TXX-92600, NUDOCS 9212220001 | |
| Download: ML20126B180 (4) | |
Text
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".",s. w i Log # TXX 92000 llll':lll" *:lllllllll Fi1e # 10010
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f 903.10 (clo)
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915.7 (clo)
Ref. # 10CFR50.34(b)
TUELECTRIC mm.m j. c.hm, Jr.
December 17, 1992 a...,, n a r,,,,.u.i U. S. Nuclear Regulatory Commission Attention:
Document Control Desk Washington, DC 20555
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES) - UNIT 2 DOCKET N05. 50-446 AND 50-446 ADVAllCE FSAR SUBMITTAL CLARIFICATION REGARDING ATTACHMENTS TO CRANES (SECTION 3.10B)
Gentlemen:
The attachment to this letter provides an advance CPSES FSAR submittal to facilitate NRC Staff review of the subject area in support of licensing Unit 2.
The attachment is organized as follows:
1.
A description / justification of each change.
2.
A copy of the revised FSAR pages (changes are indicated in the margin by a revision bar and '87').
The attached material will be incorporated in CPSES FSAR Amendment 87 which is currently scheduled for December, 1992.
If you have any questions regarding this sub..:ittal. please contact Mr. Carl Corbin at (214) 812-8859.
I Sincerely, William J. Cahill, Jr.
gy J, S. Harshall Generic Licensing Manager CBC/grp Attachment c-Mr. J. L. Hilhoan. Region IV Resident Inspectors. CPSES ( 2)
Mr. T. A. Bergman, NRR Hr. B. E. Holian. NRR 9212220001 921217 PDR ADOCK 05000445 p
' 400 N. Olive Street LD. 81 D4Has.Tenas 75201 O
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j CPSES - FINAL SAFETY ANALYSIS REPORT (FSAR)
AMEN 0HENT / REVISION 87 4
Attachment to TXX-92600 DETA! LED DESCRIPTION Pago 1 Page 1 Cf 3 i
j Prefix Page (Al M itidtd)
St9m Descriptign j
3.100-4 3
Delete the paragraph that states: All electrical 1
equipment and instrumentation mounted on or attached I
to the Containment polar crane, the Fuel Building crane the Containment rotating access platform. and the Service Water Intake Structure crane are qualified i
as seismic Category I equipment with the waiving of j
the requirement of functional operability during and j
following an SSE.
[
Clarification :
The classification and Quality Assurance requirements associated with the subject cranes are already 1
adequately described under items 34 and 35 of Table 17A 1 of the FSAR. This includes those requirements 3
related to the maintenance of structural integrity i
i and, where appropriate, support of the lifted load j
during a' seismic event. All equipment and j
instrumentation mounted on or attached to the subject cranes and not necessary for structural integrity or control of the lifted load, where appropriate, meet d
the description of REGULATORY GUIDE 1.29 SEISMIC DESIGN CLASSIFICATION. position C.2. The requirements i
for structures, systems or components meeting the description of position C.2 are described in the appropriate' sections of the FSAR (i.e. section l
3.78.2.8, last paragraph).
1 Change Request Number
- SA-92-140.1 Commitment Register Number :
Related SER-: 3.7.9.1.SSER :22 9.1.4' i
SER/SSER Impact-
- No l
15.7 10 4
In section 15.7.5 change the first sentence to read "The Comanche Peak Steam Electric Station Fuel i
Handling Building overhead crane satisfies NUREG 0554 single failure proof requirements and is designed to-j the requirements of seismic Category ~I (See Section 3.2)."
Editorial Corrected typographical error and made consistent 1 --
l with Note 53 of Table 17A-1.
Change Request Number
- SA 92-740 2 Commitment Register Number :
Related SER : 15.4.8 SSER 322 9.1.4 SER/SSER Impact
- No-i i
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Attachment to TXX-92600 CPSES/FSAR Page 2 Of 3 functional operability during and af ter an earthquake of magnitude up to and including the SSE.
Seismic design of the Reactor Protection System and ESF circuits is discussed in Section 3.10N.
87 Horizontal and vertical ground accelerations during an SSE are used to formulate floor response spectra at each equipment location as described in Section 3.78.2.
Equipment and system specifications include the appropriate response spectra used for the analysis or testing of the equipment.
The seismic qualification program for electrical equipment is as described in Section 3.78.2.1.3.
Analysis j
is used for the qualification of equipment of relatively simple j
geometry which can be modeled accurately.
Suppliers are required to furnish documentation of actual test results or detailed computations, if an v.alytical approach is used, to substantiate the capability of the equipment to perform its intended function under the specified cnditions.
69 Seismic Category 1 instrumentation and electrical equipment are seismically qualified in accordance with the procedures and documer,tatior: requirements specified in IEEE 344-1975," Recommended Practices for Seism P Oualification of Claes 1E Equipment for Nuclear 81 Power Generating Stat e s."
For eqd pment in mild environment areas, the procurement documents will require that the effects of aging on seismic qualification be assessed and, if there are aging effects, will require pre-aging or analysis of aging effects as part of the seismic qualification requirements.
l l
L Amendment 87 3.108-4
_ December 18, 1992
Attachment to TXX-92600 age 3 U 3 CPSES/FSAR 15.7.4.3.2 Postulated Fuel Handling Accident inside Containment Q212.65 66 An analysis of the r5diological consequences of a fuel handling accident inside the Cont &inment Building would use ther same assumptions and yield the same results as those of a fuel handling accident outside the Containment Building.
The accident described in the preceding section is considered to represent the limiting case; therefore, no specific analysis of such an accident inside the Containment is provided.
15.7.4.4 conclusions 66 The possibility of a fuel handling accident is relatively small due to the many physical, administrative, and safety restrictions imposed on 72 fuel handling operations.
However, based on conservative design basis parameters, the calculated doses from a postulated fuel hand 11ng accident are within the values set forth in 10CFR100.
15.7.5 SPENT FUEL CASK DROP ACCIDENTS Q212.65 87 The Comanche Peak Stean, Electric Station Fuel Handling Building overhead crane satisfies NUREG-0554 single-failure-proof requirements andisdesignedtotherequirementsofseismicCategoryI(SeeSection 3.2).
As such it can retain the maximum design load during a Safe 7
Shutdown f.arthquake and remain in place under all postulated seismic.
loadings.. The crane is also provided with interlocks which prevent a fuel cask from being lifted more than 29.25 ft above floor elevation or from passing over the new fuel storage area during the spent fuel cask modc of operation (see Section 9.1.2.2).
The crane does not pass over the spent fuel pool in any mode of operation.
Based on this.desie approach, the radiological consequences of a spent fuel cask drop - cident need not be evaluated.
Amendment 87 15.7 =-
- DGSGE3cElfk1ER______.-___