ML20035F904
| ML20035F904 | |
| Person / Time | |
|---|---|
| Site: | 05200001 |
| Issue date: | 04/21/1993 |
| From: | Fox J GENERAL ELECTRIC CO. |
| To: | Poslusny C Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 9304230042 | |
| Download: ML20035F904 (6) | |
Text
,
i GENuclear Energy
~
(.ta3:s i u ~ Ccm)any l
c 2 w: ~ aw,e
.:,e u ;c 1
l l
April 21,1993 Docket No. STN 52-001 l
t Chet Poslusny, Senior Project Manager Standardization Project Directorate Associate Directorate for Advanced Reactors and License Renewal l
Office of the Nuclear Reactor Regulation
Subject:
Submittal Supporting Accelerated ABWR Review Schedule - Chapter 8 Modifications
Dear Chet:
1 Enclosed are modifications of selected pages from Attachment 3 of my March 31,1993 letter.
i These modifications were agreed upon in our April 21,1993 telephone call.
Please provide copies of'.his transmittal to Dale Thatcher.
Sincerely, Jack Fox Advanced Reactor Programs cc: Norman Fletcher (DOE)
Bob Strong (GE)
JI W 98 e
9304230042 930421
.ppR ADOCK 05 1
l A
l
23A61a:Ac M
Rev c
- Standard Plant TABLE 1.8-21 (Continued)
INDUSTRIAL CODES AND STAND, GDS APPLICABLETO ABWR Code or Standard Title Number Year IEEE 279 1971 Criteria for Protection Systems for NGPS Criteria for Class 1E Power Systems for NPGS 308 1980 Electrical Penetration Assemblies in Containment 2
317 1983
[,,, T Structures for NPGS Qualifying Class IE Equipment for NPGS 323 Motors for NPGS, Type Tests of Continuous Duty class 1E 334 1974 Criteria for the Periodic Testing of NPGS Safety 338 1977 Systems Recommended Practices for Seismic Oualifications of 344 1987 Class IE Equipment for NPGS 379 1977 Standard Application of the Single Failure Criterion to NPGS Safety Systems Qualification of Actuators for Power Operated Valve SS2 1985 Assemblies with Safety-Related Functions for NPP Type Test of Class IE Cables; Field Splices and 3S3 1974 Connections for NPGS Criteria for Independence of Class 1E Equipment and 384 1981 Circuits Criteria for Diesel-Generator Units Applied as Standby 387 1984 Power Supplies for NPGS Practice for Maintenance, Testing, and Replacement of 450 1987 Large lead Storage Batteries for Generating Stations and Substations Recommended Practice for the Installation Design and 484 1987 Installation of Large Lead Storage Batteries for NPGS Amendment 17
s f
I'
+
MARK-UP TEXT INSERTS 1
\\
INSERT E (35 CONF)
(5) Other Criteria i
j (a) IEEE 741
" Standard Criteria for the Protection of Class lE Power Systems l
and Equipment in Nuclear Power Generating Stations" The AB'.'R fully meets the requirements of this standard.
l INSERT F (35 CONF) i (5) Other Criteria
\\
f (a) IEEE 946
" Recommended Practice for the Design of Safety-Related DC Auxiliary Power Systems for Nuclear Power Generating Stations" The ABWR fnLF7 meets the requ.^-a ts of this standard.
=-
i I
INSERT C (65 CONF) g i*s a karth en str'veus red l
M s /quipmentAis designed and qualified to surv ve the combined effects of 3
temperature, humidity, radiation, and other e itions related with a LOCA or other design-basis event environment at
- end of their qualified and/or design life.
l INSERT H (43 CONF) f 1
These overload byprsses meet the requirements of IEEE 603, and are capable of being periodically tested (see 8.3.4.24)..
4 INSERT I (71 CONF)
Section 5.2 of IEEE 308 is addressed for the ABWR as follows:
i Those portions of the Class lE power system that are required to support safety j
systems in the performance of their safety functions meet the requirements of IEEE 603.
In addition, those other normal components, equipment, and systems (that is, overload devices, protective relaying, etc) within the Class lE power j
system that have no direct safety function and are only provided to increase 1
the availability or reliability of the ClasslE power system meet those
]
requirements of IEEE 603 which assure that those components, equipment, and systems do not degrade the C1.ss lE power system below an acceptable level.
However, such elements are not required to meet criteria as defined in IEEE 603 for: operating bypass, maintenance bypass, and bypass indication."
INSERT J (72 OPEN/ CONF) i c:\\ou62\\ chb /insertsf.up March 31, 1993,
e
,ae,-~
a en,
23Af,100AE MM arv s Standard Plant applicable, these parameters are given in terms Estimated chemical environmental conditions are of a time-based profile.
als
.u J - f ymfir u The magnitude and 60-year frequency of oc
- 3.11.2 Qualification Tests and Analyses rence of significant deviations from normal ant gt, icant h)fafety-related electrical equipment :E..
J environments in the zones have insigni h:::::d ?: : 5 i -- :.
u: is qualified by^ t 6 i cffects on equipment total thermal norn I aging test or other methods as described in IEEE 323, or accident aging. Abnormal condit-'ons are
/
overshadowed by the normal or accident c' nditions in the Appendix 31 tables.
Margin is defined as the difference betwee he
)
most severe specified service conditions of t plant and the conditions used for qualification.
I Margins shall be included in the qualification parameters to account for normal variations in commercial production of equipment and reasonable errors in defining satisfactory performanec. The i
l environmental conditions shown in the Appendix 31 tables do not include margins.
Some mechanical and electrical equipment may be required by the design to perform an intended safety function between munutes of the occurrence of the event but less than 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> into the event. Such equipement shall be shown to remain functional in the accident environment for a period of at least 1 houre in excess of the time assumed in the accident anylysis unless a time margin of less than 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> can be justified.
Such justification willinclude for each piece of equipment: (1) consideration of a spectrum of breaks; (2) the potential need for the equipment later in the event or during recovery operations; (3) detemination that failure of the equipment after performance of its safety function will not be detrimental to plant safety or mislead the operator; and (5) determination that the margin applied to the minimum operability time, when combined with other test margins, will account for the uncertainties accociated with t e use of h
analytical techniques in the deris.: ion of environmental parameters, the number of units tested, production tolerances, and test equipment inaccuracies The environmental conditions shown in the Appendix 31 tables are upper-bound envelopes used to establish the environmental design and quali-fication bases of safety related equipment. The upper bound envelopes indicate that the zone data reflects the worse case expected environment produced by a compendium of accident conditions.
3.11 1.1 Amendment 21
' ABM w
23ssiome Standard Plant 7 gr u
. *f /
M n._... _ y ::r" :.q G M.a.n b.
3.11.4 IAss f Heating, Ventilating, a d Air j
Equipment type test is the preferred method of Conditio g
walification.j To ensure that loss of heating, ventilating,
-- g7phatety related mechanical equipment that is and air conditioning (HVAC) system does not
((,5) located in a harsh environment is qualified by adversely affect the operability of safety-analysis of materials data which are generally related controls and electrical equipment in based on test and operating experience, buildings and areas served by safety-related HVAC systems, the HVAC systems serving these The qualification methodology is described in areas meet the single-failure criterion.
detail in the NRC approved licensing Topical Section 9.4 describes the safety-related HVAC Report on GE's environmental qualification systems including the detailed safety evalu-program (Reference 2). This report also add-ations. The loss of ventilation calculations resses compliance with the applicable portions of are based on maximum heat loads and consider the General Design Criteria of 10CFR50, Appendix operation of all operable equipment regardless A, and the Quality Assurance Criteria of 10CFR50, of safety classification.
Appendix B. Additionally, the report describes conformance to NUREG-0588 (Reference 3), and 3.11.5 Estirnated Chernical and Radiation Regulatory Guides and IEEE Standards referenced Environrnent in Section 3.11 of NUREG-0800 (Standard Review Plan).
3.11.5.1 Chemical Environment Mild environment is that which, during or Equipment located in the containment drywell after a design basis event (DBE, as defined in and wetwell is potentially subject to water Reference 2), would at no time be significantly spray modes of the RHR system. In addition, more severe than that which exists during normal, equipment in the lower portions of the contain-test and abnormal events.
ment is potentially subject to submergence. The chemical composition and resulting pH to which safety-related equipment is exposed during normal operation and design basis accident conditions is reported in Appendix 31.
The COL applicant will require vendors of Sampling stations are provided for periodic equipment located in a mild environment to submit analysis of reactor water, refueling and fuel a certificate of conipliance certifying that the storage pool water, and suppression pool water equipment has been qualified to assure its to assure compliance with operational limits of required safety-related function in its the plant technical specifications.
applicable environment. This equipment is qualified for dynamic loads as addressed in 3.11.5.2 Radiation Environment Sections 3.9 and 3.10. Further, a surveillance and maintenance prog.am will be developed to Safety-related systems and components are ensure equipment operability during its designed designed to perform their safety-related l life. (See Subsection 3.11.6).
function when exposed to the normal operational radiation levels and accident radiation Icvels.
3.11.3 Qualification Test Results Electronic equipment subject to radiation The results of qualification tests for exposure in excess of 1000 R and mechanical safety-related equipment will be documented, equipment in excess of 10,000 R will be maintained, and reported as mentioned in qualified in accordance with Reference 1.
Subsection 3.11.6.
3.11-2 Amendment 24