ML17334A945
| ML17334A945 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 02/03/1986 |
| From: | Alexich M INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| AEP:NRC:0070V, AEP:NRC:70V, NUDOCS 8602100174 | |
| Download: ML17334A945 (22) | |
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REGULATORY IlO~MATION DlSTRIBUTION SYST~(RIDS),
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NOT RAZED:
NO FACIL: 50-31& Donald C.
Cook Nuclear Power Planti Unit 2i Indiana 8<
05000316 AUTH. NAME AUTHOR AFFILIATION ALEXICHiM. P.
Indiana Zc Michigan Electric Co.
RECIP. NAME RECIPIENT AFFILIATION DENTONi H. R ~
Office of Nuclear Reactor Regulationi Director (post 851125
SUBJECT:
Requests hydrostatic testing of identified Inservice Class 1 5 2 piping at lower pressures than 1974 ASME criteria. Avoidance of unnecessary personnel exposure radiation hazards cited. Fee paid.
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INDIANA8 MICHIGAN ELECTRIC COMPANY P.O. BOX 16631 COLUMBUS, OHIO 43216 February 3, 1986 AEP:NRC:0070V Donald C. Cook Nuclear Plant Unit No.
2 Docket No.
50.-316 License No.
DPR-74 INSERVICE INSPECTION PRESSURE TEST CODE RELIEF Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C.
20555
Dear Mr. Denton:
This submittal and its attached flow diagrams are made pursuant to 10 CFR Section 50.55a(g)(6)(i).
The piping sections listed below are classified as ISI Classes 1 and 2 and are subject to hydrostatic testing during the 1986 Refueling Outage and the subsequent 10-year ISI outage for Unit 2 in accordance with Articles IWB-5000 and IWC-5000 of the ASME Code,Section XI, 1974 Edition.
These sections of piping cannot be tested to the code requirements without modifying the systems and/or exposing personnel to unnecessary radiation hazards.
We are therefore requesting code reliefs to test the, piping at a lower pressure.
1.
Emer enc Core Cooling S stem, Flow Dia ram 2-5143 (Attached)
Pi in Boundaries (a)
Accumulator No.
1 Discharge Piping Valves IM0-110, SI-166-1, IRV-155, SI-168-1 (b)
Accumulator No.
2 Discharge Piping Valves IMO-120, SI 166 2~ IRV 165'I 168 2
(c)
Accumulator No.
3 Discharge Piping - Valves IM0-130, SI 166 3g IRV 175'I 168 3
(d)
Accumulator No.
4 Discharge Piping - Valves ZM0-140, SI-166-4, IRV-185, SI-168-4 k
ISI Code Class-2 Requirements:
For a system design pressure of 2485 psig, Article IWC-5000 of Section XI code requires the piping to be tested at a pressure of 3106 psig and temperature not less than 100 F.
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Mr. Harold R. Denton AEP:NRC:0070V Code Relief Re uest:
We propose to test the above sections of piping at a pressure of 2280 psig at a temperature above 100 F.
The test will be 0
performed during Mode 3 with the Reactor'oolant, System (RCS) pressure at 2280 psig and 7y 500 F.
The RCS pressure will be used 0
to block the check valves (SI-166-1, SI-166-2, SI-166-3, SI-166-4) closed, thus limiting maximum pressure to 2280 psig.
Basis For Relief Re est:
The section of piping upstream of check valves SI-166-1 through 4
cannot be tested at a pressure of 3106 psig without making extensive temporary modifications to keep the valves closed.
The modifications would require:
(1) disassembly of the valves, (2) welding of temporary blocks (on the downstream side) inside the valve bodies to hold a "jack screw" type arrangement to keep the valve closed, (3) removal of the temporary blocking devices from the valves after testing, and (4) performing necessary non-destructive testing to ensure the integrity of the valve bodies before returning'hem to service.
The piping downstream of these valves is part of the RHR System and carries radioactive fluid
~ during normal operation.
Therefore, plant personnel would be
'ubjected to substantial radiation exposure and radioactive contamination in order to carry out any modifications for the test.
We believe this to be a reasonable code relief request, since the proposed test pressure is, in fact, higher than the 2235 psig nominal operating pressure in the short sections (less than 5
feet) of the piping systems for which the relief is requested.
2.
CVCS - Reactor Letdown and Charging, Flow Diagram 2-5129 (Attached)
~ Pi ing Boundaries:
(a) 2-Inch Aux. Spray Piping Valves QRV-51, CS-325 (b)
Normal Charging Loop 4 Cold Leg-QRV-62, CS-328-L4, CS-326 and CS-327 (c)
Alternate Charging Line to Loop 1 Cold Leg-Valves QRV-61, CS-328-Ll ISI Code-1 Re uirement for Item.(a):
For operating pressure of 2235 psig, Article IWB-5000 of Section XI code requires the piping to be tested at a pressure 2458 psig 0
and temperature not less than 100 F.
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Mr. Harold R. Denton ISI Code Class-2 Re uirement for Items (b) and (c):
For a design pressure of 2735 psig, Article IWC-5000 of Section XI code requires the piping to be tested at a pressure of 3418 psig at temperature not less than 100 F.
0 Code Relief Re uest:
We propose to test the above sections of piping at a pressure of 2280 psig at a temperature above 100 F.
The test will be 0
performed during Mode 3 with the RCS pressure at 2280 psig and p 500 F.
The RCS pressure will be used to block the check valves 0
CS-329L1, CS-329L4 and CS-325 closed, thus limiting maximum pressure to 2280 psig.
Basis for Relief Re uest for Items 2(a), 2(b) and 2(c):
This is a similar situation to Relief Request No. 1.
Check valves CS-328L1, CS-328L4, and CS-325 are located on the charging lines to the RCS System.
These valves must be disassembled and temporarily modified to block them closed in order to perform the required hydrostatic tests and plant personnel would be exposed to high radiation and radioactive contamination during the modification.
We believe this to be a reasonable code relief request, since the proposed test pressure is, in fact, higher than 2235 psig nominal operating pressure in the sections of piping between 23 to 115 feet long for which the relief is requested.
3.
CVCS Reactor Letdown and Char ing, Flow Diagram 2-5129 (Attached)
Pi in Boundaries:
Letdown Lines Valves QRV-112, QRV-160, QRV-161, QRV-162 ISI Code Class'-2 Re uirement:
For a design pressure of 2485 psig, Article IWC-5000 of Section XI code requires the above piping to be tested, at,,a pressure of 3106 psig and temperature not less than 100 F.
0 Code Relief Request:
We propose to test the above section of piping at a pressure of 2280 psig at a temperature above 100 F during Mode 3 using RCS 0
pressure.
Valves QRV-111 and QRV-112 will be opened with QRV-160, QRV-161 and QRV-162 closed.
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Mr. Harold R. Denton AEP:NRC:0070V Basis for Relief Request:
The above section of piping cannot be tested at a pressure of 3106 psig without modification since no test connection exists.
This piping carries radioactive fluid during normal operation.
Therefore, plant personnel would be subjected to substantial radiation exposure and contamination in order to add a test connection.
I As an alternative, extending the test boundary to QCR-301 was considered.
This would involve using QPX-301'ocated on the downstream piping outside the regenerative heat exchanger room as a test connection.
This. consideration was also rejected because valve QCR-301 and the flange bolted to the inlet flange of safety valve SV-051 are 600-lb. class, which cannot withstand the above test pressure.
We believe this, to be a reasonable code relief request, since the proposed test piessure is, in fact, higher than 2235 psig nominal operating pressure in the sections of piping approximately 65 feet long for which relief is requested.
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Emergenc Core Cooling System (SIS), Drawing 2-5142 (Attached)
Piping Boundaries:
'alves Valves Valves Valves IM0-51, SI-142Ll Boron Injection IM0-52, SI-142L2 Boron Injection IM0-53, SI-142L3 Boron Injection IM0-54, SI-142L4 Boron Injection Loop No.
1 Loop No.
2 Loop No.
3 Loop No.
4 ISI Code Class 1 Re uirement:
For an operating pressure of 2235 psig, Article IWB-5000 of the ASME Code,Section XI, requires that the piping be tested at a pressure of 2458 psig and a temperature not less than 100 F.
0 Code Relief Re uest:
We propose to test the above section of piping at' pressure of 2280 psig and a temperature above 100 F.
The test'ill be 0
'performed during Mode 3 with the RCS pressure at 2280 psig and 0
7y 500 F.
The RCS pressure will be used to block check valves SI-142L1 through L4 closed, thus limiting maximum pressure at 2280 psig.
Basis for Relief Request:
This is a similar situation to Relief Request No. 1.
The sections of the piping system upstream of check valves SI-142L1 through L4 cannot be tested at a pressure 2458 psig without making temporary modifications (blocking the valve disc) to keep
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Mr. Harold R. Denton the check valves closed.
Since the piping sections are part of the primary system, plant personnel would be subjected to substantial radiation exposure and contamination in order to carry out such modifications for the test.
5.
We believe that this is a reasonable code relief request, since the proposed test, pressure is in fact higher than the 2235 psig nominal operating pressure in the sections of piping, each approximately 44 to 55 feet long, for which code relief is requested.
I Auxilia S ray to Reactor Coolant System and Pressurizer, CVCS-Reactor Letdown and Charging System, Drawin 2-5129 (Attached)
Pi in Boundaries:
Valves QRV-51 Valves QRV-61 Valves QRV-62 CS-326 CS-322 ISI Code Class 2 Re uirement:
For a design pressure "of 2735 psig, Article IWC-5000 of the ASME Code,Section XI, requires that the piping be tested at a pressure of 3418 psig, and a temperature not less than 100 F.
0 Code Relief Request:
We propose to test the above section of piping at a pressure of 2800 psig.
Basis for Code Relief:
I In order to perform the pressure test in this ISI Class 2
Sections of piping, valve QRV-51 has to be used as an isolation valve.
This 1,500-lb. class, air-operated control valve is designed to withstand test pressure of 3418 psig in the open position.
However, it cannot be used as an isolation valve because it was designed for a differential pressure of 1200 psig.
The valve cannot be kept closed, dur'ing pressure testing at 3418 psig without extensive temporary rigging.
The modification would require:
(1) removal of the air operator and installation of a "strong back" to keep the valve closed during the testing, (2) removal of the "strong back" after the testing, and (3) re-installation of the air operator on the valve and restoring the valve to operable condition before returning to service.
The valve is located inside the regenerative heat exchanger
- room, which is a very high radiation area and plant personnel would be subjected to radiation exposure of 5 to.7 man rems.
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As an alternative, the possibility of using a freeze seal plug downstream of QRV-51 was considered.
This would involve extensive working time close to the pressurizer spray valves, which are in a high radiation area.
This alternative was rejected because plant personnel would be subjected to an even higher radiation exposure of 8.5 man rems during formation, monitoring and removal of the freeze seal plug.
We believe that this is a reasonable code relief request, since the proposed test pressure is in fact higher than the normal operating pressure of 2235 psig in the approximately 30 feet long section of piping for which code relief is requested.
The NRC granted these code reliefs for Unit No.
1 hydrostatic testing in 1985 (reference NRC's letters dated June 28, 1985 and August. 13, 1985).
Attached to. this letter are the following flow diagrams:
1) 2)
3)
Dwg. No. 2-5143-29, "Emergency Core Cooling (RHR)," Unit No.
2 Dwg. No. 2<<5129-28, "CVCS Reactor Letdown and Charging."
Dwg. No. 2-5142-26, "Emergency Core Cooling (SIS)," Unit No.
2 In order to avoid unnecessary delays and to restore the unit to power on time as scheduled, we are requesting a response from the NRC by February 20, 1986. If you have any questions or concerns about the material contained herein, please do not hesitate to call us.
Although these code relief requests have been reviewed by appropriate technical and managerial personnel at both AEPSC and the Plant, this document has not yet been reviewed by our Nuclear Safety and Design Review Committee.
It will be reviewed by them at their next scheduled meeting.
A check in the amount of $150.00 is attached with this letter for the NRC processing of the aforementioned requests.
This document has been prepared following Corporate procedures which incorporate a reasonable set of controls to insure its accuracy and completeness prior to signature by the undersigned.
Very truly yours, V
Attachments M.. Al xich )g vice president eL~)d" cc:
John E. Dolan (w/o attachments)
W. G. Smith, Jr. - Bridgman (w/attachments)
R. C. Callen (w/o attachments)
G. Bruchmann (w/o attachments)
G. Charnoff (w/o attachments)
NRC Resident Inspector Bridgman (w/attachments)
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W. Jurgensen R. F. Kroeger M. L. Horvath Bridgman J. F. Stietzel Bridgman F. S. VanPelt, Jr.
J.
B. Shinnock D. L. Wigginton, NRC - Washington, D.C.
AEP!NRC:0070V DC-N-6015.1
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