ML19341C479
| ML19341C479 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 02/25/1981 |
| From: | Clayton F ALABAMA POWER CO. |
| To: | Tedesco R Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8103030606 | |
| Download: ML19341C479 (10) | |
Text
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Abbims hower Company
' 600 North 18th Street Post Offics Box 2641
~ Birmingham. Alabama 35291 Telephone 205 250-1000 m
F. L CLAYTON. JR.
1 Senior Vice President Alabama Power i
thesouthemelectrcsystem.
February 25, 1981 4
Docket No. 50-364 Director, Nuclear Reactor Regulation U. S. Nuclear Regulatory Comission Washington, D. C.
20555-Attention: Mr. Robert L. Tedesco JOSEPH M. FARLEY NUCLEAR PLANT - UNIT 2 REQUEST FOR ADDITIONAL Q-LIST INFORMATION Gentlemen:
As requested by the NRC staff in a telephone conversation February 24, 1981, Alabama Power Company hereby submits the enclosed clarification of our February 20, 1981 letter concerning the above referenced subject.
If you have any questions concerning this item, please advise.
Yours very truly,
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F. L. Clayton, Jr.
FLCjr/RWS:rt Enclosure cc: Mr. R. A. Thomas Mr. G. F. Trowbridge Mr. L. L. Kintner (w/ enclosure)
Mr. W. H. Bradford (w/ enclosure)
I QOO 3
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8103030 604
RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION CCNCERNING 0-LIST ITEMS 260.0 Quality Assurance Branch 260.3 Section 17.1.2.2 of'the standard format (Regulatory Guide 1.70) requires the identification of safety-related structures, systems, and components (Q-list) controlled by the QA program. You are requested to supplement and clarify the Q-list in the FSAR in accordance with the following:
a.
The following items do not appear on the Q-list. Add these items or justify not doing so.
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Question g
- 1) Measuring and test equipment used for safety-related structures, l
systems, and components.
Response
Administrative procedures ensure that applicable regulatory requirements, design bases, and other quality assurance requirements are included or raferenced in procurement documents for each item. These specifications and quality assurance requirement!s will vary depending on the application of each item. This system is fully documented and auditable within the Operations Quality Assurance Program. The calibration and maintenance program is also a part of the Operations Quality Assu'rance Program and is fully documented and auditable.
Question
- 2) Masonry walls per IE Bulletin No. 80-11.
Response
All masonry walls either in proximity to or with safety-related equipment attached to them will be added to the Q-list.
RESPONSE TG REQUEST FOR ADDITIONAL INFORMATION CONCERNING Q-LIST ITEMS Page 2 1
Question
- 3) Inten.tionally omitted.
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Question
- 4) Radiation monitoring (fixed and portable).
4
Response
Same as response to question number 1.
4 Question
- 5) Radioactivity m:'nitoring (fixed and portable).
Response
Same as response to question number 1.
Question
- 6) Radioactivity sampling (air, surfaces, liquids).
Response
Same as response to question number 1.
Question
- 7) Radioactive contamination measurement and analysis equipment.
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Response
Same as response to question number 1.
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RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION CONCERNING Q-LIST ITEMS Page 3 Question
- 8) Personnel monitoring internal (e.g., whole body counter) and external (e.g., TLD system).
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Response
Same as response to question number 1.
Question _
t 9)
Instrument storage, calibration, and maintenance program.
Response
The Farley Nuclear Plant instrument storage, calibration, and maintenance program is a part of the Operations Quality Assurance Program and is fully documented and auditable.
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Question
- 10) Decontamination Program Reiponse The Farley Nuclear Plant decontamination program is part of the Chemistry and Health Physics Program which is part of the Operations Quality Assurance Program and is fully documented and auditable.
Question
- 11) Respiratory protection equipment, including testing.
Response
Same as response to question number 1.
RESPONSE TO REQUEST FOR ADDITIONAL.
INFORMATION CONCERflING Q-LIST ITEMS Page 4 Question
- 12) Contamination control.
Response
The Farley liuclear Plant contamination control program is part of the Chemistry and Health Physics Program which is part of the Operations Quality Assurance Program and is fully documented and auditable.
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- b. of NUREG-0737, " Clarification of TMI Action Plan Requirements" (flovember 1980) identified numerous items that are safety-related and appropridte for OL application and, therefore, should be on the Q-list. These items are listed below. Add these items to the Q-list and/or indicate where on the Q-list
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they can be found. Othersise justify not doing so.
Question
- 1) Plant-safety-parameter display console.
(I.D.2)
Response
Alabama Power Company will address this requirement and implecentation schedule by May 17, 1981. The Operations Quality Assurance Program, which is fully documented and auditable, will apply to safety-related aspects of this equipment.
Question
- 2) Reactor coolant ' system vents.
(II.B.1)
RESPONSE TO REQUEST FOR ADDITIONAL
'INFORMATION CONCERNING Q-LIST ITEMS Page 5
Response
Reactor coolant system vents are part of the reactor coolant system pressure boundary which is presently covered by Q-List section 2.1.10.1.
Question i
- 3) Plant shielding.
(II.B.2)
Response
a Administrative procedures ensure that applicable regulatory requirements, design bases, and other quality assurance requirements are included or referenced in procurement documents for items associated with this category. These specifications and quality assurance requirecents will vary depending on the a'pplication of each item. This system is fully documented and auditable within the Operations Quality Assurance Program. The calibration and maintenance / modification
, rogram is also a part of the Operations. Quality Assurance p
Program and is fully documented and auditable.
Question
- 4) Post accident sampling.
(II.B.3)
Response
Same as response to question b.3.
Question 5). Valve position indication (II.D.3)
Response
Same as response to question b.3.
Question
- 6) Auxiliary feedwater system.
(II.E.1.1)
Response
The auxiliary feedwater system is presently covered by Q-list section 2.12.
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RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION CONCERNING Q-LIST ITEMS Page 6 Question
- 7) Auxiliary feedwater system initiation and flow (II.E.1.2)
Response
Auxiliary feedwater system initiation and flow are presently covered by section 2.12, 3.6.3 and 3.6.4 of the Q-List.
Question 1
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- 8) Emergency power for pressurizer heaters.
(II.E.3.1) f
Response
The Emergency Electrical Systems required to energize the pressurizer heaters are presently covered in the Q-list.
(section 3.11)
Question
- 9) Dedicated hydrogen penetrations.
(II.E.4.1)
Response
Since the plant design does not utilize external recombiners, nor does it primarily rely on a purge system for combustible gas control, this item does not apply to Farley Nuclear Plant.
Question
- 10) Containment isolation dependability.
(II.E.4.2)
Response
The containment isolation system is presently covered by Q-List section 1.1.2.7, 1.1.2.8 and 3.6. 3.
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RESP 0fiSE TO REQUEST FOR ADDIT 10t4AL TNFORMATION CONCERNING Q-LIST ITEMS Page 7 Question
- 11) Accident monitoring instrumentation.
(II.F.1)
Response
i The additional accident monitoring equip...ent outlined in our responses to NUREG-0737 section II.F.1 dated January 14, 1981, February 9, 1981, and February 13, 1981 will be added to the Q-list.
Question 12)
Instrumentation for detection of inadequate (II.F.2) core cooling.
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Response
i Same as response for question b.3.
Question
- 13) Power supplies for pressurizer relief valves, (II.G.1) block valves, and level indicators.
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Response
The power supplies for the pressurizer relief valves, block valves, and level indicators are presently covered in sections 3.2, 3.3, 3.4, 3.5 and 3.11 of the Q-List.
Question
- 14) Automatic PORV isolation (II.K.3(1))
Response
l The PORV's are presently covered in section 2.1.8.1 of the Q-List..
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RESPONSE TO REQUEST FOR ADDITI0f4AL INFORMATION C0iiCERNING Q-LfST ITEMS Page 8 Question
- 15) Automatic trip of reactor coolant pumps.
(II.K.3(5))
Response
This issue will be addressed subsequent to completion of the studies outlined in Alabama Power Company's response dated January 14, 1981 concerning this issue.
In the event that automatic trip of the reactor coolant pumps is required as a result of these studies, it is already covered by Q-list sections 3.6, 3.7, 3.8 and 3.9.
Question
- 16) PID controller.
(II.K.3(9))
Response
The PID controller is considered a part of the entire valve when qualified by~the vendor. The PORV is a Q item. Any PID that is re-ordered will be equivalent to the original PORV PID controller.
Question l
- 17) Anticipatory reactor trip on turbine : rip.
(II.K.3(12))
Response
Reactor protection systems are presently covered by section 3.6, 3.7, 3.8, and 3.9 of the Q-List.
1 Question
- 18) Power on pump seals.
(II.K.3(25))
Response
The emergency power supply to component cooling water pumps and centrifugal charging pumps is presently covered by sections 3.1, 3.2, 3.3, and 3.4 of the Q-List.
RESPONSE TO REQUEST FOR ADDITIONAL INFORMAT10N CONCERilING Q-LIST ITEMS Page 9 Question
- 19) Emergency plans.
(III.A.1.1/III.A.2)
. Response
.The Emergency Plan is included in the Operations Quality Assurance Program and is fully documented and auditable.
Question
- 20) Emergency support facilities.
(III.A.I.2)
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Response
The configuration / operability of the emergency support facilities are an int'egral part of the Emergency Plan which is part of the Operations Quality Assurance Program and is fully documented and auditable.
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Question 21)
Inpl. ant I2. radiation monitoring.
(III.D.3.3)
Response
Same as response for question b.3.
Testing, calibration, and utilization of these instruments is part of the Operations Quality Assurance Program and is fully documented and auditable.
Question
- 22) Control-room habitability (III.D.3.4)
_ Response Systems which ensure control-room habitability are covered in section 2.18 of the Q-List.
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Any item to be added to the Q-List as a result of this review will not be modified, upgraded, or replaced at this ti.
When such items are to be replaced / codified, the appropriate qualificat;ans, specifications, etc. will be applied to the replacement modification.