ML20213D184
| ML20213D184 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 04/14/1980 |
| From: | Butler W Office of Nuclear Reactor Regulation |
| To: | Haass W Office of Nuclear Reactor Regulation |
| References | |
| CON-WNP-0300, CON-WNP-300 NUDOCS 8005050622 | |
| Download: ML20213D184 (4) | |
Text
. _.
050 f 27 k.hk/[h'9/ y, m eq ggpy
~
o a go - 39 7 APR 141980 rEi'O MEMORANDUM FOR:
Walter P. Haass. Chief. Quality Assurance Branch, DPM FROM:
Walter R. Butler, Chief, Containment Systems Branch, DSS
SUBJECT:
Q-LIST FOR WASHINGTON PUBLIC POWER SUPPLY SYSTEM, UNIT 2 Per your mquest by memorandum dated March 7,1980, the Containment Systems Branch (CSB) provides the attached list (Attachment 1) of the safety related structures, systems and components (SSC) that fall within our area of myfew responsibility.
Systems identified by asterisks are not entimly within the review responsi-bility of the CSB. However, the subsystem listed below those systems (see ) are either within the review area of CSB or their integrity is mquired for the functioning. of systems which am within our review respon-sibility.
Based on our review of the infonation presented in Table 3.2-1 of the FSAR, we find that the applicant has not completely identified all the safety re-lated SSC that are within the area of review for the CSB. However, the QAP for those systems identified in Attachment 1 is acceptable. Attachment 2 identifies those safety related SSC that have not been listed by the appli-
' cant but which should be added to Section 3.2.
Original signed by Walter R. Butleg Walter R. Butler, Chief Containment Systems Branch Division of Systems Safety Attachments:
As stated cc: R. Denise L. Rubenstein J. Kudrick
[ Central files D. Lynch c313 Rdn
^
F. Eltawila NRR Rdg (P-428) 009BdN
Contact:
F. Eltawila, CSB: DSS 2941R o,F,ce g CSB:DSSg CSB: DSS CSB: DSS.
JKu rick..s.UBugler.,M su R Nwe >fEltawila;1f.
occ> 4/..lA /80..
4/.1./80 4/.(T!80 P0QC FORM 314 (9 76) NRCM 0240 D U.S. GOVERNMENT PRINTING OFFICE: 1979 289 369 *
-s Systems for Which QAP is Accepted
- Nuclear Boiler System relief valve discharge piping safety relief valves main steam isolation valves
- CRD Hydraulic System containment isolation valves
- Standby Liquid Control System containment isolation valves piping within isolation valves
- RHR System containment isolation valves
- Low Pressure Core Spray containment isolation valves piping, within outermost isolation valves
- Hiah Pressure Core Spray containment isolation valves
- Reactor Core Isolation Cooling System containment isolation valves piping, within outerraost containment isolation valves
- Reactor water cleanup system containment isolation valves piping within RCPB and outermost valve Primary Containment Purge System containment isolation valves
- Reactor Building Closed Cooling Water System piping and valves forming part of containment boundary
- Main Steam Isolation Valve Leakage Control System containment isolation valves piping up to outermost isolation valves
- Neutron Monitoring System TIP piping and containment isolation valves Containment /Drywell Atmosphere Monitoring System t
m
~
. Drywell Insulation
- Instrument and Service Air piping and containment isolation valves
- Sampling Systems piping and containment isolation valves i
i 4
t 1
)
m Systems for Which No QAP is Proposed Equipment and Drain Floor piping and containment isolation valves Quencher and Quencher Support Downcomers and Braces Containment Spray System
- Condensate and Feedwater System piping from RPV to outermost isolation valves containment isolation valves Primary Containment access hatches / locks / doors penetration assemblies vacuum relief va.lves
- Engineering Safety Features Actuation System Combustible Gas Control System hydrogen recombiners O
.--, -