ML19341D674
| ML19341D674 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 03/30/1981 |
| From: | Clayton F ALABAMA POWER CO. |
| To: | Schwencer A Office of Nuclear Reactor Regulation |
| References | |
| RTR-REGGD-01.097, RTR-REGGD-1.097 NUDOCS 8104080386 | |
| Download: ML19341D674 (9) | |
Text
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Mailing Address Alibama PowIr CompIny 600 Norm 18th Street Post Ofhce Box 2641 Birmingham. Alabama 35291 Telephone 20$ 783-6081 F. L. Clayton. Jr.
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Alabama Power March 30, 1981 m*rvn ewu swem
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,p.i.{.d' Docket No. 50-364
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W $9 S
Director, Nuclear Reactor Regulation g
U. S. Nuclear Regulatory Commission a
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g Washington, D.C.
20556 Attention: Mr. A. T. Schwencer 49
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Gentlemen:
N Re: Joseph M. Farley Nuclear Plant - Unit 2 R. G.1.97 Implementation Section 2.C.4 of the Farley Nuclear Plant Unit 2 low power license requires Alabama Power Company to provide a schedule for implementing the requirements of Regulatory Guida 1.97, Revision 2 (R. G. 1.97). Alabama Power Company has established and is implementing a program to address the subject requirements. This program is designed to satisfy the provisions of R. G. 1.97.
The program consists of four tasks:
1.
IDENTIFY REQUIREMENTS 2.
EVALUATE FNP-2 INSTRUMENTATION 3.
DEVELOP ACTION PLANS TO SATISFY PROVISIONS OF R. G. 1.97 4.
IMPLEMENT ACTION PLANS A preliminary review of the FNP-2 instrumentation has been completed to determine compliance with the provisions of R. G.1.97.
This review is documented via an evaluation sheet for each parameter identified in R. G. l.97, Table 2.
Evaluation sheets have been completed for types A, B, C, D, and E instruments. The Type A instruments were determined by reviewing the emergency operating procedures. This review has revealed tiiat certain provisions of the regulatory guide can not be implemented as stated therein. Attachment 1 contains a preliminary list of such provisions with an explanation for these conditions. Generally for these cases specific utilization of the FNP-2 instruments and the original design and licensing bases account for such variances. Attachment 2 is a preliminary list of the design and qualification criteria associated with R. G.1.97, Table 2 for which the FNP instrumentation requires classification different to that specified by the regulatory guide.
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Mr. A. T. Schwencer March 30, 1981 U. S. Nuclear Regulatory Comission Page 2 A detailed review of the FNP-2 instrumentation has been initiated
.0 determine the degree of compliance to the subject provisions. After the review is completed, action plans to resolve the open items will be developed. Subsequently, the action plans will be implemented. A schedule for review completion, action development and implementation is provided in.
l Regulatory Guide 1.97 requires that environmental qualification, l
seismic qualification, range, quality assurance, single failure and physical independence, human engineering, recording power supply, etc. be addressed in regard to identified instrumentation channels.
Except as modified by NUREG-0737 and the Comission Memorandum and Order which implements NUREG-0588, these subjects are scheduled to be addressed by June of 1983.
NUREG-0588 modifies only the environmental qualification recomendations for this instrumentation. Alabama Power Company is in the process of addressing NUREG-0588; however, there is a set of instrumentation that falls under both the jurisdiction of the C0 mission Memorandum and Order ead Regulatory Guide 1.97.
If o ly the NUREG-0588 requirements are addressed, it is possible that some instrumentation may be deficient in regard to other provisions in Regulatory Guide 1.97. Qualification of instruments, as necessary, which are within the scope of both Regulatory Guide 1.97 and NUREG-0588 will be undertaken in a timely manner. New instrumentation will not be installed or present instrumentation considered to be in compliance with the recomendations of Regulatory Guide 1.97 until-all of the criteria are addressed.
Alabama Power Company will provide a definitive method of qualification or documentation of such qualification for each instrument described in R. G. 1.97 based on its specific application in FNP-2. This effort will be
-implemented within a timeframe consistent with the noted deficiencies and the availability of hardware, material, testing facilities, etc. Alabama Power Company will make every effort to complete this program by June,1983.
l l
If there are any questions, please contact us.
l Yours very truly, k
b C**L,
V F. L. Claytor, Jr.
FLCJr/RLG:aw
(
Attachments cc: Mr. R. A. Thomas Mr. G. F. Trewbridge Mr. L. L. Kintner W/ Attachments)
Mr. W. ' H. Bradford W/ Attachments) y
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ATTACH:'E:l! 1 SPECIFIC R. G. 1.97 PPOVISIONS FOR FNP-2
~
I 1.
Secticc 1.3.1.a Environmental and Seismic Provisions The bans for environmental and seismic qualification in the Farley Nuclesc Plant design is IEEE-323-1971 and IEEE-344-1971, respectively.
In addi ion, compliance with NUREG-0538, Category II, cs impler.ented i
i by the Com. mission t'ecorandum and Order (CLI-80-21) has been demonstrated.
"ew ir.s.rumentaticn loops and components, however, as well as components replaced as a result of the R. G.1.97 review, will be environmentally l
qualified in accordance with IEEE-323-1974 using the methodology described in laRE3-05E3 ar.d saismically qualified in accordance with IEEE-344-1975.
2.
Secs..n 1.3.1.b SW e Failure of PA."s Indication Provision Alaba. a Pcwer Ccr:any is investigating means by which the Catetory 1 and
.2 variables defined in R. G.1.97 can be satisfactorily implemented on Farley Plant Unit 2.
In some cases this implementation may pose a severe 1
-impact on existing circuitry due to the original design concept of separation and isciation as applied to the indicator portion of safety syste s.
Due to the potential of significant modifications and required outaga time re ;uf rid to implement the single failee and separation criteria for the Pain Convol-Board and electrical systems, Alabama Power Company must thoroughly investigate all possible means of effecting these changes before compliance with the R. G. 1.97, i
implementation scheduled can be developed.
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3.
Section 1.3.1.b Ambiguity Provision J Any information ambiguities will be resolved by presently installed orocess instrumentation in the co1 trol room that bears a known relationshio to the subject variable.
Farley has'in-depth coverage of safety system instru-l mentation that is backed up by a large number of normal plant process instruments on normal regulated power that will minimize operator confusion.
Based on our preliminary review, there were no examples where a parameter was only. determinable by a redundant set of type _ A instrument loops.
i-i 4.
Section' 1.5 Human Facto'rs Evaluation f
Human Factors provisions of R. G. 1.97.will b'e addressed in' Alabama Power l
Company's response to NUREG-0700 on issuance.
5.
Section-1.3.1.d QA Provisions The deecription of-the -quality. assurance provisions applied to originally installed safety related plant instrumentation -is : included sin FSAR -
l-Section 17.1'.
FSAR:Section 17.2 describes the application-of quality Tassurance. standards (referenced in Section 1.3.1 of R.
G.- 1.97)' applied
-to the procurement, installation, testing, etc. of safety related
( Attachment -1 to APC0's Response to R. G.1.97 e
ATTACH"DT 1 Pye 2 instr:.- 1:stien 5.5ich is modified or replaced af ter plant cperation.
f;ew ::e;ifications for instruments listed in R. G.1.97 aill reference these.L standards for procurement of new equipment.
. to APC0's Response to R. 3.1.97
l I
ATTACHMENT 2 FARLEY HUCLEAR PLANT - UNIT 2 II;STRUMENT QUALIFICATION VARIANCES
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F7.0M REGULATORY GU:DE !.97 TABLE 2 Variables Review Results/ Justification 1.
Neutron. Flux The range is not required to extend from 10-0 amps to 1003 po.-ler for indicating whether reactivity control has been accomplished.
2.
- are w Rar.ge C:ntainment R.G.1.97 requires category 2 Sump Level instrumentation for verifying reactor coolant system integrity. Category 3 instrumentation may be sufficient since, for the FNP design, leak detection is accomplished primarily by means of containment radiation monitors Rll and R12 in addition to contain.t.ent cooler condensate drain level.
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3.
Core Exit Temperature
.R.G. l.97 requires a category 1 design. To implement this requirement as a backfit would require. physical separation of installed cable.
Cable would be separated in the-main control room and at the reactor vessel head.
Cable. routing at the reactor vessel head is congested and.would be difficult to-
-separate due to the fixed
. location of the.incore thermocouples in each quadrant.
Therefore,
~
category'3 instrumentation may be sufficient for FNP.
4.
Containment Effluent Radio-R.G. 1.97 recuires~ category 2 activity - Noble Gasses 'from.
instrumentation..For the FNP i
. identified. release.. points and.
fdesign, category: 3 may ba -
i
. adequate since it is backup radiation exposure rate;inside AuxiliaryL Building areas.
instrumentation.to containment pressure instrumentation-for I
breach of containment.
4
- Attachment 2 to APCo's, Response to R.G. 1.97 s
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E wa,
yariables Revieu Results/ Justification 5.
Eff!uent Radicactivity -
R.G.1.97requirescategoky2 Ncble Gisas from *uxiliary i ns tru,::en ta tion.
For FNP, Evilcing category 3 instrumertation may be sufficient sirr.e it is a b3ckup to containment pressure instrucentation for indicating breach of containment.
6.
F.hR Feat Exchanger Outlet R.G.1.97 requires category 2 Temperature instrumentation.
For FMP category 3 instrumentation may be sufficient since it is a backup instrumentation to RHR flou as an indication of RHR operation.
7.
Accurulater Tank Level R.G.1.97 requires categcry 2 instrumentation.
For FNP design, category 3 iristrumentation may be sufficient since accumulator level provides verificat1]n of technical specification ~equirements and is not a primary variable for determining if safety injection is
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operating satisfactorily.
8.
Pressurizer Heater Status R.G.1.97 requires category 2 instrumentation.
For FNP design, pressurizer heater status can be determined by means of breaker status indication on the main control board control rvitch.
In addition pressurizei pressure, level and temperature provides verificatio.1 that the pressurizer is performing its intended function.
Therefore, category 3 instrumentation may be sufficient for FNP.
9.
antainment Atmosphere Temperature R.G.1.97 requires category 2 ins?*umentation with a range frca 400F to 4000F to indicate containment cooling.
For FNP design, this variable provides primarily a method to verify technical specification requirenants.
To verify containment cooling, FNP primarily utilizes containment pressure. to APCo's Response to R.G. 1.97
i Variables Mew Rcsults/ Justification Consequently, category 3 instru-mentation may be sufficient for i
FNP.
4 Furthermore, the containment post accident temperature would reach in excess of 3000F very rapidly and would be of short duration. A state of the art device to monitor this temperature transient maj not be com.mercially available and environmentally qualified.
10.
Contain ent Su ; Water NRC design criteria requires that Temperature RHR and containment spray NPSH availability exceed the pump requirements for any possible pressure.and temperature combina-tions.
FNP teets the above design 2
i criteria. Therefore, category 3 instrumentation is sufficient for FNP.
'll.
Makeup Flow-In; Letdown' Flow-Out; R.G. 1.97 requires category 2 Volume Cor; trol: Tank Level instrumentation. 'For the FNP Ldesign category 3 instrumentation may be sufficient for these variables since pressurizer level is the pri.Tary means of verifying CVCS operation..
12.-
Component Cooling Water.(CCh)
R.G. 1.97 requires category 2 l -
Flow to ESF System-instrumentation. - For the _ FNP l
design cooling water system operation is verified primarily with component cooling water heat exchanger outlet temperature.
Category 3 flow instrumentation may be sufficient to provide l
backup verification.
113.
Area Radiation
-R.G. 1.97 requires category 2 instrumentation. A shielding study has been completed and -
. modifications:are being -
implemented as ' required by NUREG-0578 and 0737. ~For FNP,
- category 3 instrumentation may be
.Jadequate for this' application. ;.to APCo's Response to RLG. 1.97 x -
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Variables Review R2sults/ Justification 14, i:abl a Gases and Vent Flow R.G. 1.97 requires category 2
. Rate - Condeasur Air Reaioval ins t run enta tic".
For FMP design, Sjsten Exhaust this radiation nonitor is located in the turbine building. The design basis for Farley Unit 2 does not require the turbine building to be designed to meet seismic requirements.
Category 3 instrumentation may be adequate.
15.
C: Ton Plant '! ant or Multi-R.G.1.97 re.:uires category 2
- -
- :se Vent :'s:harging any of instrumentatien. The state of A::,s Ealeasa 1..d.' ant from the art monitor recently installed Ste;m Ger.ers :r Safety Relief to comply with NUREG-0737 require-
'/31ves or Atrcs;neric Dump Valves ments may not comply with R.G. 1.97 criteria. Alabama Power Company is in the process of evaluating the present qualification.
- to APCo's Response to R.G. 1.97
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