ML17334A468

Responds to NRC Final Rule 10CFR50.49 Re Electric Equipment Environ Qualification.Right to Amend Response Reserved Until Meeting W/Nrc Scheduled to Resolve Environ Qualification Deficiencies

ML17334A468
Person / Time
Site:	Cook
Issue date:	05/20/1983
From:	HERING R F INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	DENTON H R Office of Nuclear Reactor Regulation
References
AEP:NRC:0775C, AEP:NRC:775C, NUDOCS 8305260281
Download: ML17334A468 (21)

Text

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'vv rW/v'.,rv F lc Ag Ov VA l 1 I C COL 4D E.I'tr'R/OL UI I<v'>ET,R/i) o I/At,(<Rgrvi3 13 LI'i)i<"3 IL ,'33, Td 5 INDIANA L, MICHIGAN ELECTRIC COMPANY P.O.BOX 18 BOWLING GREEN STATION NEW YORK, N.Y.10004 May 20, 1983 AEP:NRC:0775C Donald C.Cook Nuclear Plant Unit Nos.1 and 2 Docket Nos.50-315 and 50-316 License Nos.DPR-58 and DPR-74 FINAL RULE ON EQUIPMENT ENVIR011MENTAL QUALIFICATION (10 CFR 50.49)Mr.Harold R.Denton, Director Office of Nuclear Reactor Regulation U.S.Nuclear Regulatory Commission Washington, D.C.20555

Dear Mr,

Denton: This letter and its Attachments respond to the NRC's final rule 10 CFR 50.49,"Environmental Qualification of Electric Equipment Important to Safety for Nuclear Power Plants" puhlished in the Federal Register., Vol.48, No.13, dated January 21, 1983, pp.2729-2734, and to the clarification letter dated April 27, 1983 (Mr.S.A.Varga of the NRC to our Mr.J.E.Dolan).More specifically, we read 10 CFR 50.49(g)as requiring that we identify the electric equipment important to safety within the scope of the rule (that is, safety related, non-safety related, and certain post-accident monitoring equipment as defined in 10 CFR 50.49(b)(1) through (b)(3)), and those equipment items which we believe to be already qualified, and to establish a goal of final environmental qualification not to exceed the end of the second refueling outage after March 31, 1982, or by March 31, 1985 (whichever is earlier), for those equipment items for which qualification has not yet been established.

Furthermore, the clarification letter referenced, above requested us to indicate whether our previous submittals comply with paragraphs (a)and (b)of 10 CFR 50.49, to describe the methods used to identify the non-safety related electric equipment defined by 10 CFR 50.49(b)(2), and to establish any qualification programs not previously described for such non-safety related equipment.

We must first note for the record that we have repeatedly attempted during the past few months to meet with the NRC staff in order to clarify and resolve the environmental qualification"deficiencies" identified in the Technical Evaluation Reports (TERs)prepared by the Franklin Research Center (FRC)under contract to the NRC (see our letter AEP:NRC:0775, dated January 24, 1983).To date, a meeting has not been scheduled so that we could achieve resolution with NRC staff on this important topic.Therefore, we reserve the right to amend this SGO5260281 830520 r'!3F<ADQCK 05000315 PDR Mr.Harold R.on-2-AEP:NRC: 0775C response until such time as we may discuss the FRC TERs with your staff and arrive at an understanding of present qualification requirements.

Furthermore, if as a result of other activities (either internally generated or in response to other regulatory issues, such as Generic Letter No.82-33)it is determined that additional equipment should be included within the scope of the final rule and/or it is determined that equipment items identified in Attachment 1 to this letter require upgrading, this letter will be correspondingly amended.With the above provisos, Attachm'ents 1 through 6 to this letter provide the information requested by 10 CFR 50.49(g)and the NRC clarification letter referenced above.Specifically, Attachment 1 provides a list of equipment which we presently believe to fall within the scope of the environmental qualification final rule.The Attachment provides a listing of equipment manufacturers and model/Plant item numbers, a brief description of each equipment item, Plant identification numbers, a reference to a System Component Evaluation Worksheet (SCEW)in our AEP:NRC:0578B submittal (dated June ll, 1982), and an indication regarding whether the equipment is believed to be qualified or if qualification has not yet been established.

Not all of these equipment items (such as certain cables and cable terminations identified as a result of the NUREG-0737 reviews)have been identified in our previous submittals on environmental qualification.

The equipment list in Attachment 1 references, in the case of equipment for which qualification has not yet been established, one or more of the other Attachments to this letter.Specifically, Attachment 2 discusses aging qualification required by Section 7.0 of the DOR Guidelines.

Attachment 3 discusses those equipment items presently identified as falling under the scope of our response to Generic Letter No.82-33 (see our letter No.AEP:NRC:0773, dated April 15, 1983).Attachment 4 discusses certain Resistance Temperature Detectors (RTDs)which will be replaced in connection with the program established to meet the requirements of 10 CFR 50, Appendix R (see our letter No.AEP:NRC:0692E, dated March 31, 1983).Attachment 5 discusses the test qualification program currently underway.,with regard to our containment spray pump motors manufactured by Reliance Electric.Where applicable, requests for final environmental qualification schedular extensions under the provisions of 10 CFR 50.49(g)are included in the Attachments to this letter.Attachment 6 to this letter provides a brief description of the methods used to identify the equipment defined by 10 CFR 50.49(b).

Mr.Harold R.~on 3 I AEP:NRC:0775C This document has been prepared following Corporate Procedures which incorporate a reasonable set of controls to ensure its accuracy and completeness prior to signature by the undersigned.

Very truly yours, Vice President RFH/os cc: J.E.Dolan-Columbus R.S.Hunter M.P.Alexich R.W.Jurgensen W.G.Smith, Jr.-Bridgman R.C.Callen G.Charnoff NRC Resident Inspector at Cook Plant-Bridgman Attachment 1 to AEP:NRC:0775C Donald C.Cook Nuclear Plant Unit Nos.1 and 2 10 CFR 50.49()E ui ment List The enclosed table contains a list of those equipment items presently known to be installed at the D.C.Cook Nuclear Plant Unit Nos, 1 and 2 and which we believe to be within the scope of 10 CFR 50.49(b)(1) through (b)(3).The identified equipment items are relied on to remain functional during and following a design basis accident.For each equipment item identified, the following information is provided in the table: AEP:NRC:0578B submittal System Component Evaluation Worksheet (SCEW)reference(s).

This reference is not intended to imply that the AEP:NRC:0578B submittal, dated June 11, 1982, provides the most up-to-date qualification data.Rather, the reference is intended to provide guidance with regard to identifying those Plant systems which utilize the equipment item~(2)Identification of the D.C.Cook Plant Unit(s)in which the equipment is installed.

(3)Equipment manufacturer(s).

(4)Equipment model or-"Plant item number(s).'*-(5)A brief description of the equipment item.(6)Plant identification (i.e., tag)number(s).

(7)An indication as to whether the equipment is qualified, or whether qualification has not yet been established.

In the latter case, an entry has been made in the table which references at least one other attachment to this letter.The referenced attachment(s) provides a description of the open item(s)and, when applicable, a request for schedular extension under the provisions of 10 CFR 50.49(g).

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At present, we do not know how many Plant surveillance and maintenance procedures will have to be revised as a result of the aging analysis findings.It is presently anticipated; however, that the aging analysis and input to be used in the revision of the surveillance and maintenance procedures will be completed by EDS Nuclear, Inc., on or before August 31, 1983.A complete revision to the D.C.Cook Nuclear Plant surveillance and maintenance procedures and the establishment of the surveillance/maintenance/replacement program will be completed by November 30, 1985.Therefore, under the provisions of 10 CFR 50.49(g), we hereby request a schedular extension to November 30, 1985for the establishment of a surveillance/maintenance/replacement program at the D.C.Cook Nuclear Plant.This request for extension applies to all those equipment items identified in Attachment 1 to this letter for which"Attachment 2" has been entered in the"Qualification Not Established" column. Attachment 3 to AFP:NRC:0775C Donald C.Cook Nuclear Plant Unit Nos.1 and 2 Generic Letter 82-33 and Regulatory Guide 1.97 (Rev.2)E ui ment Items Attachment 1 to this letter identifies certain equipment items for which"Attachment 3" has been entered in the"Qualification Not Established" column.The equipment items so identified are currently being reviewed in light of the guidance contained in Regulatory Guide 1.97, Revision 2, and under the requirements of Generic Letter 82-33 (which provides for incorporation of this review into the integrated program established by NUREG-0737, Supplement 1).As committed to by our letter AEP:NRC:0773, dated April'15, 1983, we will provide the NRC staff with a review and replacement schedule (if any)six (6)months following implementation of new Emergency Operating Procedures. Until such time as these tasks are completed and the qualification test reports are received and reviewed for acceptability, a final schedule for qualification cannot be developed. The replacement schedule (if any)will, however, consider procurement lead times, test complications, installation problems, etc.Therefore, in accordance witn the provisions oz 10 CFR 50.49 (g), a request for schedular extension of final qualification to Novembe" 30, 1985, is hereby made.for those equipment items identified as relating to Generic Letter 82-33, Supple'.ent i to NUREG-0737, and Revision 2 to Regulatory Guide 1.97, This request for schedular extension applies to both Units of the D.C.Cook Nuclear Plant.Furthermore, if (as a result of these reviews)additional equipment i,tems are ident'fied as being within the scope of the final rule and/or that equipment presently identified in Attachment 1 to this letter requires upgrading, this submittal will be amended. Attachment 4 to AEP:NRC:0775C Donald C.Cook Nuclear Plant Unit Nos.1 and 2 RTD Re lacement The H.E.Sostman Model 811901B and Rosemount Model/I'176KS Resistance Temperature Detectors (RTDs)identified in our AEP:NRC:0578B submittal (see the System Component Evaluation Vorksheet,"SCEN" Z28)are being replaced in connection with the program established to meet the requirements of 10 CFR 50, Appendix R.As noted in our letter AEP:NRC:0692E, dated Harch 31, 1983, completion of this task is scheduled for August 1985.Therefore, in accordance with the provisions of 10 CFR 50.49(g), a schedular extension to September 1, 1985, is hereby requested for final qualification of the RTDs identified above.This request is applicable to both Units of the D.C.Cook Nuclear Plant. Attachment 5 to AEF:NRC:0775C Donald C.Cook Nuclear Plant Unit Nos.1 and 2 Reliance Pump a~fotor Qualif'ication An engineering review has been conducted to ascertain the environmental qualification for the Reliance Electric containment spray pump motor, in order to determine if this motor is qualified to perform its safety function in the radiation environment outside containment (following a LOCA inside containment). Although the engineering review indicates that the pump motor will perform satisfactorily, the motor manufacturer has offered to perform a radiation test on a motorette built in the same fashion and with the same materials as those of the installed D.C.Cook Plant motor.The test is not yet complete.Reliance Electric has, however, informed us that test results will be available prior to Augus" 31, 1983.As such, a request for schedular extension is not being requested at this time. Attachment 6 to AEP:NRC:0775C Donald C.Cook Nuclear Plant Unit Nos.1 and 2 Hethods Used To Identify 10 CFR 50.49(b)E uio, ent As required by 10 CFR 50.49(g), Attachment 1 to this letter contains a list of those equipment items presently known to be within the scope of 10 CFR 50.49(b)(1) through (b)(3).The identified equipment items are relied upon to remain functional during and following a design basis accident.The actions taken to develop this list consisted of those initial actions performed for our AEP;NRC:0578B submittal (as described in Attachment 6 to that submittal), review of NUREG-0737 requirements regarding environmental qualif'cation, and reconfirmation of postulated environments by review of the appropriate FSAR sections.For each device identified as being relied upon to remain functional (i.e., pump and fan motors, solenoids, hydrogen recombiners, valve motor operators, etc.), the corresponding electrical installation which would have to w'thstand the harsh environment (i.e., cables, cable terminations, limit switches, etc.)was identified. These electrical installations have been incorporated into the equipment list in Attachment 1 to this letter.,To date, our review of-elqctrical installations serving.safety or non-safety related actuating or monitoring devices has been limited to those devices which have been identified as falling within the scope of IE Bulletin No.79-01B or 10 CFR 50.49(b)(l) through (b)(3).