ML19341C230

Forwards Addl Info,Per NRC ,Re Facility Q-list. Measuring & Test Equipment Used for safety-related Structures,Sys & Components & Masonry Walls Per IE Bulletin 80-11 Discussed

ML19341C230
Person / Time
Site:	Farley
Issue date:	02/20/1981
From:	Clayton F ALABAMA POWER CO.
To:	Tedesco R Office of Nuclear Reactor Regulation
References
RTR-NUREG-0737, RTR-NUREG-737 IEB-80-11, NUDOCS 8103020451
Download: ML19341C230 (10)

Text

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Alabtma Power Company 600 North 18th Street Post Offics Box 2641 Birmingham. Alabama 35291 Telephone 205 250-1000 b

F. L CLAYTON, JR.

senior Vice President ggg g,

the SOLthern eeC!nc System February 20, 1981 Docket No.-50-364 Director, Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C.

20555 Attention: Mr. Robert L. Tedesco JOSEPH M. FARLEY NUCLEAR PLANT - UNIT 2 RE0 VEST FOR ADDITIONAL Q-LIST INFORMATION Gentlemen:

Enclosed, as requested in your letter dated February 13, 1981, is additional information concerning the Farley Nuclear Plant Q-list.

If you have any questions concerning this item, please advise.

Yours ver p uly.

0 t'

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) pl a;

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RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION CONCERNING Q-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 :tems do not appear on the Q-list. Add these items or justify not doing so.

Question

1) Measuring and test equipment used for safety-related structures, systems, and components.

Response

Administrative procedures ensure that applicable regulatory requirements, design bases, and other quality assurance requirements are included or referenced in procurement documents for each item. These specifications and quality assurance requirements will vary depending on the application of each item. -This system is fully' documented and auditable within the Operations Quality Assurance Program.

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.

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- RESPONSE-TO REQUEST FOR ADDITIONAL INFORMATION CONCERNING Q-LIST ITEMS Pace'2 Question

5) Intentionally omitted.

Question-

-4) Radiation monitoring-(fixed and portable).

Response

Same'as response to question number

- Question

5) Radioactivity moni_toring'(fixed and por. table).

-Response-Same as response to question number 1.

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Questic$

6) (Radioactivity sampling.(air, surfaces, liquids).

Response--

Same' as. response' to question. number 1.

Question.

7) 'Radioactiv4 contamination measurement and analysis equipment.

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Resoonse Same as response to question Lnumber,1.

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RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION CONCERNING Q-LIST ITEMS Page 3 Question

8) Personnel monitoring internal (e.g., whale body counter) and external (e.g., TLD system).

Response

Same as response to question number '.

0uestion 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.

Question

10) Decontamination Program

Response

The Farley Nuclear Plant decontamination program is part of the Chemistry and Heaith Pry;ics 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.

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RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION CONCERNING Q-LIST ITEMS Pace 4 Question

12) Contamination control.

Response

L.

The Farley Nuclear 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.

Enc 1'osure 2 of NUREG-0737, " Clarification of TMI ' Action Plan Requirements" (November'1980) identified numerous items that are safety-related 'and appropriate 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 they can be found. Otherwise justify not doing so.

Question

1) ' Plant-safety-parameter di, play console..(I.D.2)

Response

t Alabama Power Company will address this requirement and implementation schedule byJMay_ 17, 1981.

Question-2)' ? Reactor coolant system vents.

.(II.B.1)

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RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION CONCERNING Q-LIST ITEMS Pace 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 3)_ Plant shielding.

(II.B.2)

Response

Administrative procedures ensure that applicable regulatory 1 requirements, design bases, and other quality assurance requirements are included or referenced in procurement c'xuments for items associated with this category.

ihese specifications and quality' assurance requirements will vary depending-on the application of each item. This system is fully documented and auditable~within the Operations Quality

. Assurance Program.

Question

'4)'

Post accident sampling.

(II.B.3)-

Response

Same as response to question b.3.

Question 5)- -Valve position indication (11.0.3)

-Same as response to question b.3.

Question

6) Auxiliary. feedwater systam.

. ( II. E.1'.1)_

Response

The _ auxiliary feedwater system isL presentlyL covered by -Q-List

-section 2.12.

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. RESPONSE TO REQUEST FOR ADDITIONAL

-INFORMATION CONCERNING-Q-LIST ITEMS Pace 6'.-

Question

7) Auxiliary feedwater system initiation and flow (II.E.1.2)

Resoonse Auxiliary feedwater system initiation and ficw are presently covered by.section 2.12, 3.6.3 and 3.6.4 of the Q-List.

Question r

8) Ecergency. power for pressurizer heaters.

(II.E.3.1)

Response

The Emergency Electrical Systems required to energize the pressurizer heaters are presently covered in the Q-list.

'(section 3.11)

Question

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9) 0edicated. hydrogen penetrations..

(II.E.4.1)

Resconse

-Since. the. plant design does not utilize external recc=biners,

.nor does it primirily rely on a purge' system for combustible

- gas control, this. item does not apply to-Farley Nuclear Plant.

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-Question 110)-. Containment isolation dependibility.

(II.E.4.2) _

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Resconse The containment itsiation system;is presently covered by Q-List

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section-1.1.2.7, 1.1'.2.8 and 3.6.3.

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RESPONSE TO REQUEST FOR ADDIT 10NAL INFORMATION CONCERNING Q-LIST ITEMS Page 7 Question

11) Accident monitoring instrumentation.

(II.F.1)

Response

The additional accident monitoring equipment 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.

Response

Same as response for question b.3.

-Question

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13)- Power supplies for pressurizer relief valves, (II.G.1) block. valves, and level indicators.

. Response

-The power supplies for the pressurizer. relief valves, block-valves, and level indicators are presently covered Lin sections 3.2, 3.3, 3.4, 3.5 and 3.11 of ' the Q-List.

.Questioni

14) Automatic ' PORV isolation -

(II.K.3(1))

-Response The FORV's are presently covered:in section 2.1.8.1 of the Q-List.:

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RESPONSE TO REQUEST FOR ALDITIONAL INFORMATION CONCERNING Q-LIST 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.

Question:

16) PID controller.

(II.K.3(9))

Response,

'he 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 17)- Anticipatory reactor trip on turbine trip.

(11.K.3(12))

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Response

Reactor protection systems are. presently covered by section 3.6,-3.7,'3.8, and 3.9.of the Q-List.

Qu'estion

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.

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c RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION CONCERNING Q-LIST ITEMS Page 9 J '

Question

19) Emergency plans.

(III.A.

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)

Response

The emergency support facilities will be or have been built in accordance with sound engineering practice taking into consideration natural phenomena that may occur at the' site. These facilities will be able to perfor... their design functions.

Question 21)

Inplant I2 radiation monitoring.

(III.D.3.3)

Response

Same as response for question L.3.

Testing, calibration, and utilization of these instruments is part of the Operations

-Quality Assurance _ Program dnd 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.

. Any. item to be~ added.to the Q-List as a result of this review will not be-modified, upgraded,_ or--replaced at this. time. When such ' items are to be

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-replaced / modified,' the appropriate qualifications, specifications,'etc. will

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be applied:to the replacement modification.

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