ML20030C523
| ML20030C523 | |
| Person / Time | |
|---|---|
| Site: | Callaway  |
| Issue date: | 08/12/1981 |
| From: | Tedesco R Office of Nuclear Reactor Regulation |
| To: | Bryan J UNION ELECTRIC CO. |
| References | |
| TASK-***, TASK-TM NUDOCS 8108270001 | |
| Download: ML20030C523 (6) | |
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AUG 121981 LB#1 Rdg TERA DEisenhut f3RC/PDR BJYoungblood L/PDR GEdison NSIC Docket No.: STN 50-483 Maushbrook TIC RLTedesco ACRS (16)
RVollmer Mr. Ahn K. Bryan TMurley Vice President RHartfield,'1PA Union Electric Company RMattson Post Office Box 149 OELD St. Louis, Missouri 63166 OIE (3)
JSpraul
Dear Mr. Bryan:
WHaass
Subject:
Request for Additional Information for the Review of the Callaway Plant, Unit 1 Regarding Quality Assurance As a result of our continuing review of the Callaway Plant, Unit 1 FSAR, we find that we need additional information to complete our evaluation. The specific information required is in the area of quality assurance and is presented in the Enclosure.
To maintain our licensing review schedule for the Callaway Plant FSAR, we will need responses to the enclosed request by August 25, 1981.
If you cannot meet tnis date please infonn us within seven days after receipt of this letter of the date you plan to submit your responses so that we may review our schedule for any necessary changes. Please note that a draft copy of this question was provided to your staff on August 6, 1981.
Please contact Dr. G. E. Edison, Callaway Licensing Project Manager, if you desire any discussion or clarification of the enclosed request.
Sincerely, 5
Robert L. Tedesco, Assistant Director for Licensing Division of Licensing DJ.{4,/,.
Enclosure:
As stated cc: See next page k-
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Nyoaa 388710 001 NNCM O240 OFFICIAL RECORD COPY q uM 1980-329824
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' fir. J. K. Bryan Vice President - Nuclear Union Electric Company P. O. Box 149-St. Louis, Missouri 63166 L
cc: Mr. Nicholas A. Petrick Mr. William Hansen i
Executive Director - SNUPPS Resident Insoector/Callaway NPS 5 Choke Cherry Road c/o USNRC t
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Rockville, Maryland 20850 Steedman, Misso ari 65077 l
Gerald Charnoff, Esq.
l Shaw, Pittman, Potts &
1 Trowbridge 1800 M Street, N. W.
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Washington, D. C.
20036 fir. J. E. Birk Assistant to the General Counsel I
Union Electric Company P. O. Box 149 j
St. Louis, Missouri 63166 l
Dr. Vern Starks i
Route 1, Box 063 j
Eetchikan, Alaska 99901 4.
i Ms. Trevallearn, Asristant General Counsel Missouri Public Service.'camission i
P. O. Box 360 Jef ferson City, Missouri 65102 1
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Mr. D. F. Schnell j
!ianager-Nuclear Engineering Union Electric Company
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P. O. Box 149 St. Louis, Missouri 63166 i
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CALLAWAY Request for Additional Information 260.0 Quality Assurance Brar.ch 260.71C Section 17.1.2.2 of the standard format (Regulatory Guide 1.70) requires the identification of safety-related structures, systems, and components. con-trolled by the QA program.
You are requested to supplement and clarify Tcble 3.2-1 of the Callaway FSAR in accordance with the following:
i a.
The following items do nc,t appear on FSAR Table 3.2-1.
Add the appro-priate items to the table and provide a commitment that the remaining items are subject to the pertinent requirements of the FSAR operat.ional quality assurance program or justify not doing so.
1.
Safety-related masonry walls (see IE Bulletin No. 80-11).
2.
Biological shielding within the fuel building, a~uxiliary building, control building, and reactor building.
3.
Missile barriers within the fuel building, auxiliary building, control building, diesel-generator building, and essential service water pump house.
4.
Spent fuel pool liner.
5.
Refueling machine.
l 6.
Spent fuel handling tool.
7.
Radiation shielding doors.
8.
Radiation monitoring (fbed and portable).
9.
Radiocctivity monitoring (fixed and portable).
10.
Radioactivity sampling (air, surfaces, liquids).
11.
Radioactive contamination measurement and analysis.
12.
Personnel monitoring internal (e.g., whole body counter) and external (e.g., TLD system).
4 13.
Instrument storage, calibration, and maintenance.
14.
Decontamination (facilities, personnel, and equipment).
15.
Respiratory protection, including testing.
16.
Contamination control.
2-17.
Radiation shielding (permanently installed).
- 18. Accident-related meteorological data collection equipment.
19.
Expendable and consumable items necessary for the functional performance of safety-related structures, systems, and compo-nents (i.e., weld rod, fuel oil, boric acid, snubber oil, etc.).
20.
Roof drains and parapets of buildings which house safety-related equipment.
21. Site draina.ge system including grading, culverts, and channels.
l l
22.
Steam generators (primary and secondary sides).
23.
Steam generator piping located inside containment.
24.
Valve operators for all safety-related valves.
- 25. Motors for all safety-related pumps.
i b.
The following items from FSAR Table 3.2-1 need expansion and/or clari-fication as noted.
Revise the list as indicated or justify not doing so.
I l
1.
Identify the safety-related instrumentation and control systems to the same scope and level of detail as provided in Chapter 7 of the FSAR.
(This can be done by footnote.)
Verify that this includes l
I&C for:
l l
a) Contairment Spray System (1.5) b)
Containment Pooling System (1.6) c)
Containment Hydrogen Control System (1.8) l d)
Containment pressure indication e) Containment water level indication f)
Containment hydrogen indication 2.
For the systems shown below, expand the list in Table 3.2-1 to include the indicated components under the pertinent 10 CFR 50 Appendix B quality assurance requirements or verify that they art included as part of the components already listed.
1.5 Containment Spray System Containment sump 1.6 Containment Cooling System Ductwork
=
+
18 Containment Hydrogen Control System Piping and Valves 2.7 Ultimate Heat Sink Retention pond slopes Retention pond rip rap
- c. of NUREG-0737, " Clarification of TMI Action Plan Require-ments" (November 1980) identified numerous iteras that are safety-related and appropriate for OL application and therefore should be on f
Table 3.2-1.
These items are listed below. Add the appropriate items i
to Table 3.2-1 and provide a commitment that the remaining items are subject to the pertinent requirements of the F5AR operational QA pro-gram or justify not dcing so.
j NUREG-0737 l'
Clarification Item 1)
Plant safety-parameter display console.
I.D.2 2)
Reactor coolant system vents.
II.B.1 3)
Plant shielding.
II.B.2 4)
Post accident sampling capabilities.
II.B.3 t
5)
Valve position indication.
II.D.3 i
- 6) Auxiliary feedwater system.
II.E.1.1 l
- 7) Auxiliary feedwater system initiation and flow.
II.E.1.2 8)
Emergency power for pressurizer heaters.
II.E.3.1 l
9)
Dedicated hydrogen penetrations.
II.E.4.1 l
10)
Containment isolation dependability.
II.E.4.2
- 11) Accident monitoring instrumentation.
I I. F.1 l
12)
Instrumentation for detection of inadequate I
core-cooling.
II. F.2 13)
Power supplies for pressurizer relief valves, block valves, and level indicators.
II.G.1
- 14) Automatic PORV isolation.
II.K.3(1)
- 15) Automatic trip of reactor coolant pumps.
II.K.3(5) j l
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.. 16) PID controller.
I I. r,. 3 ( 9 )
- 17) Anticipatory reactor trip on turbine trip.
II.K.3(12) 18)
Power on pump seals.
II.K.3(25)
- 19) Emergency plans (and related equipment).
III. A. l.1/I I I. A.2
- 20) Equipment and other items associated with the emergency support facilities.
III.A.1.2 21)
Inplant 1 radiation monitorins.
III.D.3.3 2
- 22) Control-room habitability.
III.D.3.4
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