PY-CEI-NRR-1208, Responds to NRC 900613 Request for Addl Info Re Inservice Insp Relief Requests.Util Revised Relief Requests PT-001 & PT-003 to Provide More Detailed Info & Has Withdrawn Relief Request IR-017.Revised Relief Requests & Summary Encl
| ML20058N148 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 08/10/1990 |
| From: | Lyster M CENTERIOR ENERGY |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| PY-CEI-NRR-1208, NUDOCS 9008130265 | |
| Download: ML20058N148 (23) | |
Text
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' PERRY NUCLEAR POWER PLANT Mad Address:
10 CENTER ROAD P.O. BOX 97 Michael D. Lyster PERRY OHIO 44081 PERRY, OHIO 44081 Vice President Nuclear (2@2H37 :
August- 10, 1990 PY-CEI/NRR-1208 L U.S; Nuclear Regulatory Commission Document Control Desk Washington, D. C. 20555 Perry Nuclear Power Plant Docket No. 50-440
, ' CEI Response to NRC Request for M ' Additional Information re i Inservice Inspection Relief Requests Centlement By letter dated' June 13, 1990, the NRC staff requested additional information j
~ regarding Perry Nuclear Power. Plant (PNPP) Inservice Inspection Relief l Requests PT-001, PT-002, PT-003 and IR-017 in order,to complete a review of 'I
~e leven" relief requests submitted by the Cleveland Electric Illuminating :l Company'(CEI)-via letter:PY-CEI/NRR-1078L dated November 17, 1989.
.l 1
Based upon a telephone conversation with the NRC Staff and its contractor EG&G .)
(on July 13,:1990, CEI has, revised Relief Requests PT-001, PT-002'and PT-003 to l
. provide more detailed information, and has withdrawn Relief Request IR-017. !
In; addition, CEI hereby. withdraws. Relief < Request IR-016. Attachment 1
- E 'contains the revised relief requests and Attachment 2 contains a summary of the; reasons for the relief request withdrawals.
Attachment 3'provides clarification of the relief requested in Preservice Relief. Request fil (and subsequently resubmitted as Inservice Relief RequestL IR-009) with regard to the NRC staff's evaluation in, Appendix Q of the Perry p LSSER No. 7.
-l j If you have'any questions, please-feel free to call.
Sincerely, (
b l* . Michael D. Lyster ;
l MDL:CJP:nje
' Attachment l
O .cc: NRR Project Manager
~Sr. Resident Inspector j USNRC Region III '
EG&G Idaho, Inc. ,D Operating Units: \ \
Cleveland Electnc liluminating 9008130265 900810 Toledo Edison PDR. ADOCK 05000440 PDL O
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h PY-CEI/NRR-1208 L Attachment 1 Page 1 of 19 Perry Nuclear Power Plant Unit 1 RELIEF REQUEST #PT-001 Page 1 of 8
- 1. Identification of Components
.i Class 2 systems / components attached to the Reactor Coolant Pressure Boundary (Class 1) which are not provided with either pressure or test isolation (i.e., instrumentation, drain, vent, and test piping). A list of valve numbers identifies the affected components (i.e., valves, ,
piping systems and instruments). '
II. ASME'B&PV Section XI Requirements IVA-5213(c) Test Condition Holding Time, " System Inservice Tests - no '
L holding time required, provided the system has been in operation for at least 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />."
IVC-5210(a)(2) Test, "A system pressure test conducted during a system inservice test [IVA-5211(c)] for those systems required to operate during normal plant operation."
l III. Relief Request L . Relief is requested from using the requirement of - operating the system for four hours before commencing the VT-2 examinations - for Class 2 components and instruments non-isolable from the Reactor Coolant l . Pressure Boundary (Class 1). These components shall-be examined (VT-2 l
Visual Examination) during the Class 1 Reactor Coolant Boundary System Leakage Pressure Test at the frequency intervals: specified within Subsection. IVC. Thus, this relief request proposes substituting L IVA-5213(a) for IVA-5213(c) and IVB-5210(a)(1)-for IVC-5210(a)(2).
I .,
IV. Basis for Relief Numerous components attached to the reactor coolant pressure boundary are covered by the' provisions of 10CFR50.55a(c) Reactor Coolant Pressure Boundary. The following excerpt from 10CFR50a(c) is provided:
l
"(2) Components which are connected to the reactor coolant system and are part of the reactor coolant pressure boundary as defined in Section 50.2 need not meet the requirements of paragraph (c)(1) of this section, ,
Provided:
(1) In the event of postulated failure of the component during normal reactor operation, the reactor can be shut down and cooled i l down in an orderly manner, assuming makeup is provided by the L reactor coolant makeup system; or 1'
L
PY-CEI/NRR-1308 L Attachment 1 p Page 2 of 19 Perry Nuclear Power Plant 1 RELIEF REQUEST #PT-001 Page 2 of 8 (ii) The component is or can be isolated from the reactor coolant-system by two valves in series (both closed,~both open,_or one closed and the other open). Each open valve must-be capable of automatic actuation and, assuming the other valve is open, its closure time must be such that, in the event of postulated failure of the component during normal reactor operation, each valve remains operable and the reactor can be shut down and cooled down in an orderly manner,' assuming makeup is provided by the reactor coolant makeup system only."
The piping systems and their associated compenents connected to the reactor coolant pressure boundary'and less than 1 inch in diameter vere constructed to the requirements of ASME Code, Section III, Subsection NC, and identified as Safety Class 2 for inservice inspection. The associated components and component parts are identified by valve number and. listed below. These piping systems shall be pressurized during the Class 1 reactor coolant pressure boundary System Leakage Pressure Test and a VT-2 Visual Examination vill be performed. The System Leakage Pressure Test frequency and pressure vill be that required for a class 2 System Inservice Test. Although_the system vill not have been in operation for four hours prior to commencing the examinations, the time required to bring the reactor coolant system up to test pressure vill allow for the-detection of leakage.
Within ASME Section XI the test conditions (i.e., pressure, temperature and hold time ) between the reactor coolant pressure boundary and other safety systems are different. Although there are differences, all the system pressure tests ensure leak tightness. Therefore, the substitution of IVA-5213(a) for IVA-5213(c) and the substitution of IVB-5210(a)(1) for IVC-5210(a)(2) satisfies the intent of the Code.
.V. Alternate Examination N/A, VT-2-Visual Examination is performed.
= Valve No. Description P&ID No.
.1B33-F068A/B Recire Pump A/B Discharge Valve Vent D-302-601, 602 1B33-F070A/B Recire Pump A/B Discharge Valve Drain D-302-601, 602 1B33-F065A/B Recire Loop A/B FCV Drain D-302-601, 602 1B33-F647A/B Recire Loop A/B FCV Vent D-302-601, 602 1B33-F686A/b Recirc Loop A/B FCV Drain D-302-601, 602
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PY-CEI/NRR-1208 L Attachment 1 Page 3 of 19 q
~l Perry Nuclear Power Plant Unit 1 RELIEF REQUEST #PT-001 Page 3 of 8 l 1
Valve No.- Description P&ID No. ;
J 1833-F025A/B Recirc Pump A/B Suction Valve Vent D-302-601, 602 )
1B33-F027A/B Recire Pump A/B Suction Valve Drain D-302-601, 602' 1B33-F503A/B Instrument Isolation Valves for dPT-N015A/B, D-302-602
-F504A/B Respectively l 1B33-F505A Instrument Isolation' Valves for FT-N014C/D D-302-602 -1
-F506A 1B33-F505B Instrument' Isolation Valves for FT-N011B and D-302-602 ,
-F506B FT-N024C/D 1B33-F507A Instrument Isolation Valves for FT-N011A and D-302-602
-F508A FT-N014A/B
-1B33-F507B Instrument Isolation Valves for FT-N024A/B D-302-602 ,
L
--F508B l l 1B33-F512A/B Recirc Pump A/B Diff Pressure Instrument Vent D-302-602 -l i
1B33-F513A/B Recirc Pump A/B Diff Pressure Instrument Vent D-302-602-1B33-F577- Recirc' Loop B Flow Instrument Vent D-302-602 g 1B33-F578 Recirc Loop B Flov Instrument Vent D-302-602 1B33-F579 Recire Loop A Flow Instrument Vent- D-302-602 1B33-F580 Recirc Loop A Flow Instrument Vent D-302-602
-.1B33-F581 Recirc Loop B Flov Instrument Vent D-302-602 L IB33-F582- Recire Loop B Flow Instrument Vent .D-302-602 P
IB33-F583: Recire Loop A Flow Instrument Vent D-302-602 1B33-F584 Recirc Loop A Flov Instrument Vent D-302-602 1B33-F059' Rectre System Sample Isolation D-302-602
'1B33-F019 Reactor Vater Sample Isolation- D-302-602 1B33-F110 Rx Recirc Sample Line Drain D-302-602 1G33-F507- Instrument. Isolation Valve for FT-N037 D-302-671 I 1G33-F523 RVCU Bottom Head Flow Instrument Vent D-302-671 .;
1E32-F506A Instrument Isolation Valves for PT-N051A, D-302-341
-F544A- PT-N061A' 1E32-F506E- Instrument Isolation Valves for PT-N051E, D-302-341
-F544E PT-N061E 1E32-F506J Instrument Isolation Valve for PT-N051J, D-302-341
-F544J. PT-N061J
.1E32-F506N Instrument Isolation Valve for PT-N051N D-302-341
-F544N' PT-N061N 1B21-F596 1B21LF016~ Test Connection Root Valve D-302-121 1B21-F017- MST. Drain and MSIV Bypass Line Drain D-302-121 1N27-F551A/B/C Feedvater Header A Branch Test Isolation D-302-082 1N27-F551D/E/F Feedvater Header B Branch Test Isolation D-302-082 1N27-F557A/B Feedvater Header A/B First Test Connection D-302-082 1G33-F508A/B Instrument Isolation Valves for PT-N076A, D-302-671, 962 PT-N076B l 1
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PY-CEI/NRR-1208 L Attachment 1 l Page 4-of 19 Perry Nuclear Power Plant Unit 1 RELIEF REQUEST #PT-001 Page 4 of 8 Valve No. Description P&ID No.
1G33-F108 Pen 131 INBD Test Conn First Isolation Valve D-302-671
'1E31-F540B RVCU Diff Flow LD Lov Side Test Connection D-302-962 1E31-F541B RWCU Diff Flow LD High Side Test Connection D-302-962-1E51-F528A/B/C/D Instrument Isolation Valves for PT-N084A/B, D-302-632, 961 PT-N085A/B 1E31-F542A/B RCIC/RHR ST Supply LD Low Stby Tet t Conn D-302-961 1E31-F543A/B RCIC/RHR ST Supply LD High Stby Test Conn D-302-961 1E31-N084B-G Cross-Tie Lov Side PT-N084A/B D-302-961 1E31-N084B-R Cross-Tie High Side PT-N084A/B D-302-961
.1E31-F519 Instrument Isolation Valve For PT-N080A D-302-705, 962 1E31-F545A RHR A to LPCS LD High Side Test Connection D-302-962
-1E31-F523 Instrument Isolation Valve for PT-N081 D-302-701, 962 1E31-F547 HPCS to SLC Ref Diff Pressure Test Connection D-302-962 1E31-F520 Instrument Isolation Valve for PT-N080A D-302-642, 962 1E31-F544A RHR A to LPCS LD Low Side Test Connection D-302-962 1E31-F521 Instrument Isolation Valve for PT-N080B D-302-642, 962 1E31-F522 Instrument Isolation Valve for PT-N080B D-302-642, 962 1E21-F502 LPCS to Rx Line Test Connection D-302-705
-1E22-F501 HPCS to Rx Line Test connection D-302-701-1C41-F501 SLC Discharge.Line Inboard Dryvell Drain V1v D-302-691 1E12-F508A LPCI From RHR A Inbd First Test Connection D-302-642 1E12-F508B LPCI.From RHR B Inbd First Test Connection- D-302-642 1E12-F508C LPCI From RHR C Inbd First Test Connection D-302-642-1E12-F501 Shutdown Cooling Suction Udr Inbd First Conn D-302-642 1E51-F072 RHR & RCIC Steam Supply Line Test Connection D-302-632 1B33-F514 Recire Jet Pump 15 Flov Instrument Vent D-302-604 1B33-F515 Recirc Jet. Pump 12 Flow Instrument Vent D-302-604 1B33-F516 Recire Jet Pump 18 Flov Instrument Vent D-302-604
'1B33-F517 Recire Jet Pump 19 Flow Instrument Vent- D-302-604 1B33-F518 Recire Jet Pump 15 Flow Instrument Vent D-302-604 1B33-F519 Recirc Jet Pump 16 Flov Instrument Vent D-302-604 1B33-F520 Recire Jet Pump 17 Flow Instrument Vent D-302-604-1B33-F521 Recirc Jet Pump 11 Flov Instrument Vent D-302-604 1B33-F522 Recire Jet Pump 13 Flov Instrument Vent D-302-604 1B33-F523 Recire Jet Pump 20 Flow Instrument Vent D-302-604 1B33-F524 Recire Jet Pump 20 Flov Instrument Vent D-302-604 1B33-F525 Recirc Jet Pump 14 Flov Instrument Vent D-302-604 1B33-F526 Recirc Jet Pump 15 Flov Instrument Root D-302-604 FT-N038B, LT-N044D 1B33-F527 Recirc Jet Pump 12 Flov Instrument Root D-302-604 FT-N037F 1
PY-CEI/NRR-1208 L
' Attachment 1 Page 5 of 19 Perry Nuclear Power Plant Unit 1 RELIEF REQUEST #PT-001 Page 5 of 8 Valve No. Description P&ID No.
'1B33-F528 Recirc Jet Pump 18 Plow Instrument Root D-302-604 FT-N037M
- 1B33-F529 Recire Jet Pump 19 Flov Instrument Root D-302-604 FT-NO37S 1B33-F530- Recire Jet Pump 15 Flov Instrument Root D-302-604 FT-N0370, FT-N038B E1B33-F531 Recire Jet Pump 16 Flov Inst Root FT-N037D D-302-604 1B33-F532 Recire Jet Pump 17 Flow Inst Root FT-N037H D-302-604 1B33-F533 Recire Jet Pump 11 Flov Inst Root FT-NO37B D-302-604 1B33-F534 Recire Jet Pump 13 Flov Inst Root FT-NO37K D-302-604 1B33-F535 Recirc Jet Pump 20 Flov Inst Root FT-N038D D-302-604 1833-F536 Recire Jet Pump 20 Flov Inst Root FT-N037V, D-302-604 FT N038D
'1B33-F537 Recirc Jet Pump 14 Flow Inst Root FT-N037P D-302-604 1B33-F646 Jet Pump Post Accident Sample Isolation D-302-604 1P87-F001 Reactor Recirc B Sample Isolation Valve D-302-431,
'1B33-F538 Recire Jet Pump 7 Flow Instrument Vent D-302-603 1B33-F539 Recire Jet Pump 9 Flow Instrument Vent D-302-603
'1B33-F540- Recire Jet Pump 10 Flov Instrument Vent- D-302-603 11B33-F541 Recirc Jet Pump 1 Flov Instrument Vent D-302-603 1B33-F542. Recirc Jet Pump 2 Flow Instrument Vent D-302-603
.1B33-F543- Recire Jet Pump 5 Flow Instrument Vent D-302-603'
'1B33-F544 Recire Jet Pump 3 Plow Instrument Vent D-302-603-11B33-F545 Recirc Jet Pump 10 Plow Instrument Vent. D-302-603 1B33-F546 Recire Jet Pump 5 Flow Instrument Vent D-302-603 1B33-F547 Recirc Jet Pump 4 Plow Instrument Vent. D-302-603 1B33-F548- Recire Jet Pump 6 Flov Instrument Vent D-302-603 1B33-F549 Recire Jet Pump 8 Plow Instrument-Vent D-302-603
~1B33-F550 Recire Jet Pump 7 Flov Instrument Root D-302-603 FT-N037G 1B33-F551 Recire Jet Pump 9 Flov Instrument Root D-302-603 FT-NO37R 1B33-F552 Recirc Jet Pump 10 Plov Instrument Root D-302-603 FT-N037V, FT-N038C 1B33-F553 Recire Jet Pump.1 Flov Instrument Root D-302-603 FT-N037A 1B33-F554 Recirc Jet Pump 2 Flow Instrument Root D-302-603 FT-N037E 1B33-F555 Recire Jet Pump 5 Flow Instrument Root D-302-603 FT-N038A, LT-N044C 1833-F556 Recirc Jet Pump 3 Flov Instrument Root D-302-603 FT-N037J 1
PY-CEI/NRR-1208'L Attachment 1 Page 6 of 19 l
Perry Nuclear Power Plant Unit 1 RELIEF REQUEST HPT-001 1 Page 6 of 8 l l
, Valve No. . Description P&ID No. l 1B33-F557 Recirc Jet Pump 10 Flov Instrument Root D-302-603 FT-NO38C .l
'1B33-F558 Recirc Jet Pump 5 Flov Instrument Root D-302-603 !
FT-N037T, FT-N038A 1B33-F559 Recire Jet Pump 4 Flov Instrument Root D-302-603 FT-N037N ,
.1B33-F560 Recire Jet Pump 6 Flow Instrument Root D-302-603 FT-NO37C 1B33-F561 Recirc Jet Pump 8 Flow Instrument Root D-302-603 FT-N037L 1B33-F570 Jet Pump Flov Instrument Vent D-302-603 1B33-F571 Jet Pump Flow Instrument Isolation FT-N037G, D-302-603 FT-N037R, FT-N037V, FT-NO37A,- FT-N037E, FT-N037J, FT-NO37T, FT-NO37N, FT-NO370, 5
FT-N037L 1B33-F645 Jet Pump Post Accident Sample Isolation D-302-603 1P87-F007 Reactor Recire A Sample Isolaton Valve D-302-431 1E31-F503 . Instrument Isolation Valves for PT-N003A, D-302-961
-F504 PT-N086A, PT-N086B 1E31-F505 Instrument Isolation Valves for PT-N086C, D-302-961
-F506- PT-N086D q 1E31-F507 Instrument Isolation Valves for PT-N003B, D-302-961
-F508 PT-N087A, PT-N087B 1E31-F509 . Instrument Isolation Valves for'PT-N087C, D-302-961 )
-F510 PT-N087D- i 1E31-F570 Main Steam Line A Flow Instrument Test Conn D-302-961 'i 1E31-F571 Main Steam Line A Flov Instrument Test Conn D-302-961. ll
.1E31-F572 Main Steam Line A Flow Instrument Test Conn D-302-961 "1E31-F573 Main Steam Line A Flow Instrument-Test Conn .D-302-961
~1E31-F574 Main Steam Line B Flov Instrument Test Conn D-302-961 1E31-F575 Main-Steam Line B Flow Instrument Test Conn D-302-961 1E31-F576 Main Steam Line B Flov Instrument Test conn D-302-961 i 1E31-F577 Main Steam Line B Flow Instrument Test Conn D-302-961
-1E31-F511 Instrument Isolation Valves'for PT-N088A, D-302-961 ;
-F512 PT-N088B
'1E31-F513 Instrument Isolation Valves for PT-N003C, D-302-961 .h
-F514 PT-N088C, PT-N088D f 1E31-F515 Instrument Isolation Valves for PT-N089A, D-302-961
-F516 PT-N089B i 1E31-F517 Instrument isolation Valves for PT-N003D, D-302-961 ;
-F518 PT-N089C, PT-N089D 1E31-F578 Main Steam Line C Flov Instrument Test Conn D-302-961 j 1E31-F579 Main Steam Line C Flov Instrument Test Conn D-302-961 1
PY-CEI/NRR-1208 L.
Attachment 1 Page 7 of 19 Perry Nuclear Power Plant Unit 1 RELIEF REQUEST #PT-001 Page 7 of 8 d
Valve No. Description P&ID No. l
-1E31-F580 Main Steam Line C Flov Instrument Test Conn D-302-961
.1E31-F581 Main Steam Line C Flov Instrument Test Conn D-302-961 3 Main Steam Line D Flov Instrument Test Conn 1E31-F582 D-302-961 1E31-F583 Main Steam Line D Flov Instrument Test Conn D-302-961 !
1E31-F584 Main Steam Line D Flow Instrument Test Conn D-302-961 1E31-F585 Main Steam Line D Flow Instrument Test Conn D-302-961 1B21-F512 Instrument Isol Valve for LT-N027, LT-N017 D-302-606 <
1B21-F514 Instrument Isol Valve for LT-N095B, PT-N403B, D-302-606 PI-R004B, PT-N058, PT-N403F, PT-N068B, PT-N008B, PT-N068F, PT-N040, PT-N078B, PT-N062B, PT-N004B, LT-N080B, LT-N490, UT-N091B, LT-N402B, LT-N091F,'dPI-R009B, LT-N081B 1B21-F510 Instrument Isolation Valve for PT-N078D, D-302-606 LT-N080D, LT-N073L, LT-N073R, LT-N081D, LT-N402F, LT-N044D 1B21-F542 RPV Level Instrument Line Drain D-302-606 1B21-F511 Instrument Isolation Valve for LT-N080D, D-302-606 3 dPI-R005 *
'1B21-F544 RPV Level Instrument Line Vent D-302-606 1B21-F546 RPV: Level Instrument Line Drain D-302-606 i 1B21-F515 Instrument Isolation Valve for LT-N080B, D-302-606 LT-N004, LT-N017, LT-N027, LT-N095B 1B21-F551 RPV Level Instrument Line Vent D-302-606 1B21-F540 RPV Level Instrument Line Drain D-302-606 !
1B21-F545 RPV Level Instrument Line Vent D-302-606 I 1B21-F509 Instrument Isolation Valve for LT-N073L, D-302-606 UT-N073R, LT-N081D, LT-N402F i 1B21-F548- RPV Level Instrument.Line Drain D-302-606
.1B21-F549 RPV Level Instrument Line Vent D-302-606 1B21-F513 Instrument Isolation Valve for LT-N081B, D-302-606 LT-N091F, dPI-R009B, LT-N402B, LT-N091B.
1B21-F583 Instrument Isolation Valve for PT-N081, D-302-606, 962 dPT-NO32 1B21-F582 Jet Pump Instrument Line Vent D-302-606 '
1B21-F585 Instrument Isolation Valve For dPT-N011, D-302-606, 872 .,
dPT-N008 1B21-F523 Instrument Isolation Valve for Flow D-302-606, 604, Instruments P009, dPI-R005, LT-N490, 671 dPT-N032, FT-NO37, FT-N032, dPI-R005 1B21-F584- Jet Pump Instrument Line Vent D-302-606 l
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PY-CE1/NRR-1208 L Attachment 1 Page 8 of 19 Perry Nuclear Power Plant Unit 1 RELIEF REQUEST #PT-001 Page 8 of 8 Valve No. LDescription P&ID No.
=IB21-F553- Instrument Isolation Valve for LT-N095A, D-302-606 PT-N403A, PI-R004A, PT-N403E, PT-N005, PT-N068A. PT-N050, PT-N068E, PT-N006, PT-N008A, PT-N078A, PT-N062A, LT-N004A, LT-N080A, LT-N010, LT-N091A, LT-N402A, uPI-R009A, LT-N091E, LT-N081A 1D21-F505 Instrument Isolation Valves for LT-N0800, D-302-606 PT-N078C, LT-N004C, LT-N073G, LT-N402E, LT-N073C, LT-N081C, LT-N044C 1B21-F536 RPV Level Instrument Line Drain D-302-606 1B21-F506 Instrument Isolation Valve for LT-N0800, D-302-606~
~LT-N004C-IB21-F539 RPV Level Instrument Line Vent D-302-606 1B21-F528 'RPV Level-Instrument Line Drain D-302-606 1B21-F552 Instrument Isolation Valve for LT-N080A, D-302-606 LT-N004A, LT-N095A 1 1B21-F533 RPV Level. Instrument Line Vent D-302-606 1B21-F535- RPV Level Instrument Line Drain D-302-606 1B21-F504 . Instrument 1 solation Valves for LT-N081C, D-302-606 LT-N073C,; LT-N402E, LT-N073G 1B21-F534- RPV. Level' Instrument Line Vent D-302-606 1B21-F529' RPVLLevel Instrument LIne Drain D-302-606 71B21-F555 Instrument Isolation Valve for LT-N081A, D-302-606 UT-N091E, dPI-R009A, LT-N402A, LT-N091A, LT-N010 21B21-F531 RPV Level-Instrument Line Vent D-302-606 0
PY-CEI/NRR-1308 L Attachment 1 Page 9 of 19-Perry Nuclear Pover Plant Unit 1
- RELIEF REQUEST #PT-002 Page 1 of 8 I. Identification of Components Class 2 systems / components attached to the Reactor Coolant Pressure Boundary-(Class 1) which are not provided with either pressure or test isolation (i.e., instrumentation, drain, vent, and test piping). A list of valve numbers identifies the affected components (i.e., valves, piping systems and instruments).
II. ASME B&PV Section XI Requirements IVC-5210(a)(3) Test, "A system hydrostatic pressure test [IVA-5211(d)]
for each system or portion of systems and for repaired or replaced components, or altered portions of systems."
IVC-5222(a) System Hydrostatic Test, "The system hydrostatic test pressure shall be at least 1.10 times the system pressure P for ?
systemswithDesignTemperatureof200'Forless,andatlek$t1.25 times the system pressure P g for systems with Design Temperature above 200'F. Thesystempressureh g shall be the lovest pressure setting amongthenumber-ofsaf.etyor!eliefvalvesprovidedforoverpressure-protection within the-boundary-of the system to be tested. For systems (or portions of systems) not provided with safety or relief valves, the-system design pressure Pd shall be substituted for Pgy".
III. Relief Requested !
Relief is requested from using the Class 2 System Hydrostatic Pressure Test requirements for Class 2 components and instruments non-isolable l from the Reactor Coolant Pressure Boundary (Class 1). 'These components shall be examined (VT-2 Visual Examination) during the Class 1 Reactor- j Coolant Pressure Boundary System Hydrostatic Pressure Test at the -l frequency' intervals specified within Subsection IVB. Thus, this relief request proposes substituting IVB-5210(a)(2) for IVC-5210(a)(3) and ;
IVB-5222/IVB-5230 for IWC-5222(a).
IV. Basis For Relief Numerous components attached to the Reactor Coolant Pressure Boundary are covered by the provisions of 10CFR50.55a(c) Reactor Coolant Pressure Boundary. The following excerpt from 10CFR50.55a(c) is provided: l
9 . g l PY-CEI/NRR-1808 L Attachment 1 Page 10 of 19 Perry Nuclear Power Plant Unit 1 RELIEF REQUEST IPT-002 Page 2 of 8
"(2) Components which are connected to the reactor coolant system and are part of the reactor coolant pressure boundary as defined in Section 50.2 need not meet the requirements of paragraph (c)(1) of this section, Provided:-
'(1) In the event of postulated failure of the component during normal reactor operation, the reactor can be shut down and cooled down in an orderly manner, assuming makeup is provided by the' reactor coolant makeup systems or (11) The component is or can be isolated from the reactor coolant system by.two valves in series (both closed, both open, or one closed and the other open). Each open valve must be capable of automatic actuation and, assuming the other valve is
' open, its closure time must be such that, in the event of postulated failure of the componcat during normal reactor ,
operation, each valve remains operable and the reactor can be l shut down and cooled down in an orderly manner, assuming makeup is provided by the reactor coolant makeup system only." j
.The piping systems and their associated compon ats less than 1 inch in diameter vere constructed to the requirements of ASHE Code, Section III, i Subsection NC, and identified as Safety Class 2 for inservice inspection, j The associated components and component parts are identified.by valve number and listed below. These piping' systems shall be pressurized during the Class.1 System Hydrostatic Pressure Test and a VT-2 Visual Examination ,
~ vill be performed. The frequency and hold time of the system hydrostatic l t pressure tests are identical for Class 1 and Class 2. j 4
Vithin ASME Section XI the test conditions (i.e., pressure and .
i temperature) between the reactor coolant pressure boundary and_other safety systems'are different. The Class 1 test pressure has a maximum !
limit of 1127.5 psig (
Reference:
Table .IVB-5222-1, Test Pressure) wit.h i the Class 2 having its minimum test pressure at 1379 psig (Referencet ;
IVC-5222(a) for design temperature greater than 200 degrees F). Because j the piping systems and their associated components less than 1 inch in :j diameter for which relief is requested are non-isolable from the reactor l coolant pressure boundary, and the maximum test pressure for the Class 1 reactor ceolant pressure boundary System Hydrostatic Test is less than a
.the minimum test pressure required for a Class 2 System Hydrostatic Test, hydrostatic testing of these Class 2 components is necessarily limited to j the Class 1 System Hydrostatic Test pressure. Although there are differences, both the Class 1 and Class 2 hydrostatic pressure tests 1 ensure structural integrity and leak tightness. Therefore, the d substitution of IVB requirements for IVC satisfies the intent of the Code.
V. Alternate Examination N/A, VT-2 Visual Examination is performed.
L: -
PY-CEI/NRR-1208 L Attachment 1
."i Page 11 of 19 Perry Nuclear Power Plant Unit 1 RELIEF REQUEST #PT-002 Page 3 of 8 Valve No. Description P&ID No.
1B33-F068A/B Recirc Pump A/B Discharge-Valve Vent D-302-601, 602
- 1B33-F070A/B Recirc Pump A/B Discharge Valve Drain D-302-601, 602 1833-F065A/B Recire Loop A/B-FCV Drain D-302-601, 602
-1B33-F647A/B Recire Loop A/B FCV Vent D-302-601, 602 IB33-F606A/B Recirc-Loop A/B FCV Drain D-302-601, 602 1 B33-F025A/B Recire Pump A/B Suction Valve Vent D-302-601, 602
'1B33-F027A/B Recire Pump A/B Suction Valve Drain D-302-601, 602
'1B33-F503A/B Instrument Isolation Valves for dPT-N015A/B, D-302-602
-F504A/B Respectively 1B33-F505A' Instrument Isolation Valves for FT-N014C/D D-302 -602
--F506A
'1B33-F505B Instrument Isolation Valves for FT-N011B and D-302-602
-F506B FT-N024C/D 1B33-F507A Instrument Isolation Valves for FT-N011A and D-302-602
-F508A FT-N014A/B 1B33-F507B Instrument Isolation Valves for FT-N024A/B D-302-602
-F508B
.1B33-F512A/B Recire Pump A/B Diff Pressure Instrument Vent D-302-602 1B33-F513A/B Recirc Pump A/B Diff Pressure Instrument Vent D-302-602 1B33-F577 Recire Loop B Flow Instrument Vent- D-302-602 1B33-F578 'Recirc Loop B Flow Instrument Vent D-302-602 1B33-F579 Recire Loop A Flow Instrument Vent D-302-602
- 1B33-F580. Recire Loop A Flov Instrument Vent D-302-602 1B33-F581- .Recirc Loop.B Flow Instrument Vent D-302-602 1B33-F582 Recire Loop B Flow Instrument Vent D-302-602 1B33-F583' -Recirc Loop-A Flow Instrument Vent D-302-602 1B33-F584 Recire Loop A Flov Instrument Vent D-302-602~
1B33-F059 Recire System Sample Isolation D-302-602
'1B33-F019 Reactor Vater Sample Isolation D-302-602
- 1B33-F110- Rx Recire Sample Line Drain D-302-602
'1B33-F020. Reactor Vater Sample Isolation D-302-602 1B33-F021- Recire System Sample Test Connection D-302-602
'1G33-F507- Instrument Isolation Valve for FT-N037 D-302-671 1G33-F523 RVCU' Bottom Head Flow Instrument Vent D-302-671 1E32-F506A Instrument Isolation Valves for PT-N051A, D-302-341
-F544A PT-N061A
- 1E32-F506E Instrument Isolation Valves for PT-N051E, D-302-341
-F544E PT-N061E 1E32-F506J Instrument Isolation Valve for PT-N051J, D-302-341
-F544J PT-N061J 1E32-F506N Instrument Isolation Valve for PT-N051N D-302-341
-F544N PT-N061N
. - - - . - - - n.
i
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PY-CEI/NRR-1208 L Attachment 1 Page 12 of 19 Perry Nuclear Power Plant Unit 1 RELIEF REQUEST #PT-002 Page 4 of 8 Valve No. Description P&ID No.
- t IB21-F596 1B21-F016 Test Connection Root Valve D-302-121 IB21-F017 MST Drain and MSIV Bypass Line Drain D-302-121 IN27-F551A/B/C Feedvater Header A Branch Test Isolation D-302-082 IN27-F551D/E/F Feedvater Header B Branch Test Isolation D-302-082 IN27-F557A/B Feedvater Header A/B First Test Connection D-302-082 1G33-F508A/B Instrument Isolation Valves for PT-N076A, D-302-671, 962-PT-N076B -
IG33-F108 Pen 131 INBD Test Conn First Isolation Valve D-302-671 1E31-F540B RVCU Diff Flov LD Low Side Test Connection D-302-962 1E31-F541B RVCU Diff Flow LD High Side Test Connection D-302-962 1E51-F528A/B/C/D Instrument Isolation Valves for PT-N084A/B, D-302-632, 961 PT-N085A/B IE31-F542A/B RCIC/RHR ST Supply LD Low Stby Test Conn D-302-632, 961 1E31-F543A/B RCIC/RHR ST Supply LD High Stby Test Conn D-302-632, 961 1E31-N084B-G Cross-Tie Low Side PT-N084A/B D-302-961 ,
IE31-N084B-R Cross-Tie High Side PT-N084A/B D-302-961 1E31-F519- Instrument Isolation Valve For PT-N080A D-302-705, 962 1E31-F545A RHR A to LPCS LD High Side Test Connection D-302-962 11E31-F523 Instrument Isolation Valve for PT-N081 D-302-701, 962 1S31-F547 HPCS to SLC Ref Diff Pressure Test Connection D-302-962 1E31-F520 Instrument Isolation Valve for PT-N080A D-302-642, 962 '
1E31-F544A _RSR A to LPCS LD Low Side Test Connection D-302-962-
.1E31-F521 Instrueent Isolation Valve for PT-N080B D-302-642, 962 1E31-F522 Instrument Isolation Valve for PT-N080B D-302-642, 962 1E21-F502 LPCS to Rx Line Test Connection D-302-705 i
1E22-F501 HPCS tv FG: Line Test ec.nection D-302-701 1C41-F501 SLC Discharge Lins Inboard Dryvell Drain V1v D-302-691 1E12-F508A- LPCI'From RHR A Inbd First Test Connection D-302-642 1E12-F508B LPCI From RHR B Inbd First Test Connectica D-302-642 l 1E12-F508C 'LPCI From RHR C Inbd First Test Connection D-302-642 1E12-F501 Shutdown Cooling Suction.Hdr-Inbd First Conn D-302-642 1E51-F072 RHR & RCIC Steam Supply Line. Test Connection D-302-632 1B33-F514 Recirc Jet Pump 15 Flov Instrument Vent D-302-604
-1B33-F515 Recirc Jet Pump 12 Flow Instrument Vent D-302-604 1B33-F516 Recire Jet Pump 18 Flov Instrument Vent D-302-604
-1B33-F517 Recire Jet Pump 19 Flow Instrument Vent D-302-604 L, IB33-F518 Recire Jet Pump 15 Flow Instrument Vent D-302-604
-1B33-F519 Recirc Jet Pump 16 Flov Instrument Vent D-3U2-604 1B33-F520 Recirc Jet Pump 17 Flow Instrument Vent D-302-604 l -1833-F521 Recire Jet Pump 11 Flow Instrument Vent D-302-604 L 1B33-F522- Recirc Jet Pump 13 Flow Instrument Vent D-302-604 1 IB33-F523 Recire Jet Pump 20 Flov Instrument Vent D-302-604 l
PY-CEI/NRR-1200 L Attachment 1 L Page 13 of 19 Perry Nuclear Power Plant Unit 1 RELIEF REQUEST #PT-002 Page 5 of 8 Valve No. Description P&ID No.
IB33-F524 Recire Jet Pump 20 Flov Instrument Vent D-302-604
'1833-F525 Recire Jet Pump 14 Flov Instrument Vent D-302-604
- 1B33-F526 Recirc Jet Pump 15 Flow Instrument Root D-302-604 FT-N038B, LT-N044D 1B33-F527 Recirc Jet Pump 12 Flow Instrument Root D-302-604 FT-NO37F 1B33-F528 Recirc Jet Pump 18 Flov Instrument Root D-302-604 FT-N037H-1B33-F529 Recire Jet Pump 19 Flov Instrument Root D-302-604 FT-NO37S IB33-F530 -Recirc Jet Pump 15 Flov Instrument Root D-302-604 FT-NO370, FT-NO38B
-1B33-F531 Recire Jet Pump 16 Flow Inst Root FT-NO37D -D-302-604 1B33-F532- Recire Jet Pump 17 Plow Inst Root FT-N037H D-302-604 1B33-F533 Recire Jet Pump 11 Flov Inst Root FT-N037B D-302-604 1B33-F534 .Recire Jet Pump 13 Plow Inst Root FT-NO37K= D-302-604 1B33-F535 Recirc Jet Pump 20 Flov Inst Root FT-N038D D-302-604 1B33-F536 Recire Jet Pump 20 Flow Inst Root FT-NO37V, D-302-604 FT-N038D 1B33-F537 Recire Jet-Pump 14 Flov Inst Root FT-N037P D-302-604 1B33-F646 Jet Pump Post Accident Sample Isolation D-302-604 1P87 r'001 Reactor Recire B Sample Isolation Valve D-302-431 1B',3-F538 Recire Jet Pump 7 Flow Instrument Vent D-302-603
433-F539
. Recire Jet Pump 9'Flov Instrument Vent D-302-603 1B33-F540 Recire Jet Pump 10 Flov Instrument Vent D-302-603 1B33-F541 Recirc Jet Pump 1 Flov Instrument Vent D-302-603 IB33-F542 Recire Jet Pump 2 Flov Instrument Vent D-302-603 11B33-F543 Recire Jet Pump 5 Flow Instrument Vent- D-302-603 1B33-F544 Recire Jet Pump 3 Flow Instrument Vent D-302-603 1B33-F545 Recire Jet Pump 10 Plov Instrument Vent D-302-603 IB33-F546 Recirc Jet Pump 5_ Flow Instrument Vent D-302-603 1B33-F547 Recirc' Jet Pump 4 Flov Instrument Vent D-302-603 1B33-F548 Recire Jet Pump 6 Flow Instrument Vent- D-302-603 1B33-F549_ Recirc Jet Pump 8 Flow Instrument Vent D-302-603 IB33-F550 Recire Jet Pump'7 Flov Instrument Root D-302-603 FT-N037G 1B33-F551 Recirc Jet Pump 9 Plov Instrument Root D-302-603 FT-NO37R 1B33-F552 Rocire Jet Pump 10 Flow Instrument Root D-302-603 FT-N037V, FT-N038C IB33-F553 Recirc Jet Pump 1 Flov Instrument Root D-302-603 FT-NO37A
IT ]
y '
'." j'; '
PY-CEI/NRR-1208 L Attachment 1 Page 14 of 19 Perry Nuclear Power Plant Unit 1 RELIEF REQUEST #PT-002 Page 6 of 8 Valve No. Description- P&ID No.
IB33-F554 Rectre Jet Pump 2 Flov Instrument Root D-302-603 '
FT-N037E 1B33-F555- Recire Jet Pump 5 Flov Instrument Root D-302-603 FT-NO38A, LT-N044C 1B33-F556 Recirc Jet Pump 3 Flov Instrument Root D-302-603 FT-NO37J 1B33-F557 : Recirc Jet Pump 10 Flov Instrument Root D-302-603 FT-N038C-1B33-F558 _Recirc Jet Pump 5 Flow Instrument Root D-302-603 FT-NO37T, FT-N038A IB33-F559 Recirc Jet Pump 4 Flov Instrument Root D-302-603 FT-N037N 1B33-F560 Recirc Jet Pump 6 Flov Instrument Root D-302-603 '
FT-N037C
-1B33-F561 Recirc Jet Pump 8 Plov Instrument Root D-302-603 FT-N037L 1B33-F570 Jet Pump Flow Instrument Vent D-302-603 1 1B33-F571 Jet Pump Flov Instrument Isolation FT-N037G, D-302-603 FT-N037R,.FT-NO37V, FT-N037A, FT-N037E, 1 -
FT-NO37J, FT-N037T,.FT-NO37N, FT-N037C, FT-N037L 1B33-F645 Jet Pump Post Accident Sample-Isolation D-302-603
'1P87-F007 Reactor Recire A Sample Isolaton Valve- D-302-431 1E31.-F503 . Instrument Isolation Valves for PT-N003A, .D-302-961
-F504 PT-N086A, PT-N086B 1E31-F505 Instrument Isolation Valves for PT-N0860, D-302-961 .i
-F506 PT-N086D 1E31-F507 Instrument' Isolation Valves for PT-N003B, D-302-961'
-F508 PT-N087A, PT-N087B~
1E31-F509 Instrument Isolation Valves for PT-N087C, D-302-961
-F510~ PT-N087D 1E31-F570 Main Steam Line A Flov Instrument Test Conn D-302-961 1E31-F571 Main Steam Line A Flow Instrument Test Conn D-302-961
-1E31-F572 Main Steam Line A Flow Instrument Test Conn D-302-961 ,
1E31-F573 Main Steam Line A Flow Instrument Test Conn D-302-961
~1E31-F574 Main Steam Line B Flov Instrument Test Conn D-302-961 ;
1E31-F575 Main Steam Line B Flow Instrument Test Conn D-302-961 1E31-F576 Main Steam Line B Flow Instrument Test Conn D-302-961 1E31-F577 Main Steam Line B Flov Instrument Test Conn D-302-961 1E31-F511 Instrument Isolation Valves for PT-N088A, D-302-961
-F512. PT-N088B 1E31-F513 -Instrument Isolation Valves for PT-N003C, D-302-961
-F514 PT-N088C, PT-N088D
t -t . . .
PY-CEI/NRR-1208 L Attachment 1 Page 15 of 19 Perry Nuclear Power Plant Unit 1 RELIEF REQUEST #PT-002 Page 7 of 8
-Valve No. Description P&ID No.
1E31-F515 Instrument Isolation Valves for PT-N089A, D-302-961
-F516 PT-N089B 1E31-F517 Instrument isolation Valves for PT-N003D, D-302-961
-F518 PT-N089C, PT-N089D 1E31-F578 Main Steam Line C Flov Instrument Test Conn D-302-961 1E31-F579 Main Steam Line C Flow Instrument Test Conn D-302-961
'1E31-F580 Main Steam Line C Flov Instrument Test Conn D-302-961 1E31-F581 Main Steam Line C Flov Instrument Test Conn D-302-961 1E31-F582 Main Steam Line D Flov Instrument Test Conn D-302-961 1E31-F583 Main Steam Line D Flov Instrument Test Conn D-302-961 1E31-F584 Main Steam Line D Flov Instrument Test Conn D-302-961 1E31-F585 Main Steam Line D Flov Instrument Test Conn D-302-961 1B21-F512 Instrument Isol Valve for LT-N027, LT-N017 D-302-606 1B21-F514 Instrument Isol Valve for LT-N095B, PT-N403B, D-302-606 PI-R004B, PT-N058, PT-N403F, PT-N068B, PT-N008B, PT-N068F, PT-N040, PT-N078B, PT-N062B, PT-N004B, LT-N080B, LT-N490, LT-N091B, LT-N402B, LT-N091F, dPI-R009B, LT-N081B 1B21-F510 Instrument Isolation Valve for PT-N078D, D-302-606 LT-N080D, LT-N073L, LT-N073R, LT-N081D, LT-N402F, LT-N044D 1B21-F542 RPV Level Instrument Line Drain D-302-606 1B21-F511 Instrument. Isolation Valve for LT-N080D, D-302-606 dPI-R005
'1B21-F544 RPV Level Instrument Line Vent D-302-606
~1B21-F546 -RPV Level Instrument Line Drain D-302-606
- 1B21-F515 Instrument Isolation Valve for LT-N080B, D-302-606 LT-N004, LT-N017, LT-N027, LT-N095B 1B21-F551 RFV Level Instrument Line Vent D-302-606 1B21-F540 RPV Level Instrument Line Drain D-302-606 1B21-F545 RPV Level Instrument Line Vent D-302-606 1B21-F509 Instrument Isolation Valve for LT-N073L, D-30?-606 LT-N073R, LT-N081D, LT-N402F 1B21-F548 RPV Level Instrument Line Drain D-302-606 1B21-F549 RPV Level. Instrument Line Vent D-302-606 IB21-F513 Instrument Isolation Valve for LT-N081B, D-302-606 LT-N091F, dPI-R009B, LT-N402B, LT-N091B
'1B21-F583 Instrument Isolation Valve for PT-N081, D-302-606, 962 dPT-NO32 1B21-F582 Jet Pump Instrument Line Vent D-302-606 1B21-F585 Instrument Isolation Valve For dPT-N011, D-302-606, 872 dPT-N008
E ., ,;
PY-CEI/NRR-1808 L Attachment 1 Page 16 of 19 Perry Nuclear Power Plant Unit 1 RELIEF REQUEST #PT-002 Page 8 of 8 LValve No. Description P&ID No.
1B21-F523 Instrument Isolation Valve for Flow D-302-606, 604, Instruments P009, dPI-R005, LT-N490, 671 dPT-NO32, FT-NO37,.FT-N032, dPI-R005-1B21-F584 Jet Pump Instrument Line Vent D-302-606 1B21-F553 Instrument Isolation Valve for LT-N095A, D-302-606 PT-N403A, PI-R004A, PT-N403E, PT-N005, PT-N068A, PT-N050, PT-N068E, PT-N006, PT-N008A, PT-N078A, PT-N062A, LT-N004A, LT-N080A,'LT-N010, LT-N091A, LT-N402A, dPI-R009A, LT-N091E,-LT-N081A
--1B21-F505 Instrument Isolation Valves for LT-N0800, D-302-606 PT-N078C, LT-N004C, LT-N073G, LT-N402E, LT-N0730, LT-N081C, LT-N044C IB21-F536 RPV Level Instrument Line Drain- D-302-606 1B21-F506 Instrument = Isolation Valve for LT-N0800, D-302-606 LT-N004C 1B21-F539 RPV' Level Instrument Line Vent D-302-606 1B21-F528- RPV Level Instrument Line Drain D-302-606 1B21-F552; . Instrument Isolation Valve for LT-N080A, D-302-606 UT-N004A, LT-N095A 1B21-F533 RPV Level Instrument Line' Vent D-302-606 IB21-F535 RPV Level Instrument Line Drain- D-302-606 1B21-F504 Instrument-Isolation Valves for LT-N0810, D-302-606 LT-N073C, LT-N402E,..LT-N073G 1B21'F534
- RPV Level Instrument Line Vent D-302-606 1B21-F529 RPV Level Instrument LIne Drain D-302-606 1B21-F555- Instrument Isolation Valve for LT-N081A, D-302-606
-LT-N091E, dPI-R009A, LT-N402A, LT-N091A, LT-N010 1B21-F531 RPV Level Instrument Line Vent D-302-606
g a:
PY-CEI/NRR-1208 L t Attachment l ;
Page 17 of 19 Perry Nuclear Power Plant RELIEF REQUEST DPT-003 Page 1 of 3 I. Identification of Components Class 2 and 3 components which undergo routine quantitative L pressurization tests in which no detectable leakage vould be identified :
as the minimum equipment accuracy (i.e., normally inclusive of valves, piping systems and penetrations). A listing of test pressurization
boundaries are identified by penetration number.
L II. ASME B&PV Section XI Requirements i IVA-5211 Test Description, "The pressure retaining components within
.each -system boundary shall be subject to system pressure tests under which conditions visual examination VT-2 is performed in accordance with IVA-5240 to' detect leakages. The required system pressure tests and examinations, as referenced in Table IVA-5210-1, may be conducted in conjunction with one or more of the following system tests or operationst "(b) a system functional test, (d)'a system hydrostatic test, and (e) a system pneumatic test.
' IVA-2500(a) Examination anu Pr---" 2 Test Requirements, " Components shall be examined and pressure tested as specified in Table IVC-2500-1.
-The method of examination for the components and parts of the pressure I retaining boundaries shall comply with those tabulated in Table IVC-2500-1, except where alternate examination methods are used that meet the requirements of IVA-2240."
IVC-5210(a) Test, "The pressure retaining components within each system boundary shall be subjected to the following system pressure tests and i visually examined by the method specified in Table IVC-2500-1, 2 Examination Category C-4: "(1) a system pressure test conducted during a system functional test, and (3) a system hydrostatic pressure test, i IWC-5210(b) Test, "The system pressure tests and visual examinations shall be conducted in accordance with IVA-5000 and this Article. The.
contained fluid in_the system shall serve as the pressurizing medium, except that in steam system either water or air may be used. Where air is used, the test procedure shall permit the detection and location of ,
through-vall leakages in components of the system tested." '
4 4
PY-CEI/NRR-1208 L Attachment 1 Page 18 of 19 '
Perry Nuclear Power Plant RELIEF REQUEST #PT-003 Page 2 of 3 IVD-2500(a) Examination and Pressure Test Requirements, " Components shall be examined and pressure tested as specified in Table IVD-2500-1.
The method of examination for the components and parts of the pressure retaining boundaries shall comply with those tabulated in Table
.IVD-2500-1 except where alternate examination methods are used that' meet the requirements of IWA-2240."
IVD-5210(a) Test, "The pressure retaining components within the boundary of each system specified in the Examination Categories of Table IVD-2500-1 shall be pressure tested and examined in accordance with Table IVD-2500-1 during the following tests:" "(2): system functional >
tat, IVA 5211(b); (3) system hydrostatic test, IVA-5211(d)." ,
III.. Relief Requested Relief is. requested from performance of VT-2 Visual Examination in conjunction with a system pressure test where the test pressurization 1 boundary leakage is' measured (makeup or pressure decay) and quantified as within the test equipment accuracy (no detectable leakage). The test. ..'
pressurization boundaries are identified by penetration numbers. The boundary includes components and appurtenances-which become pressurized during testing. '
l:
.IV. Basis For Relief Numerous-Class 2 and 3 components undergo leak testing.using the pressure.make-up or pressure decay techniques. These tests require the measurement and quantification of the test pressurization boundary a leakage. Perfor'mance of a VT-2 Examination vould require walkdowns and' 1 may involve scaffolding erection in radiation areas. Pressure testing i using air could additionally require insulation removal (and re-installation) for detecting leakage by VT-2 Visual Examination. The j use of an alternative technique of no detectable-leakage meets the ALARA policy at'PNPP. The majority of pres'sure tests are to satisfy' plant Technical Specifications for verifying plant component operability and structural' integrity. The test equipment used to satisfy Technical Specifications has an accuracy and range unique to verify major safety concerns. The quantification as no detectable leakage is documented as minimum equipment accuracy (i.e., 20 seem or 4.8 ml/ min). The performance of a VT-2 Visual Examination during testing would not serve a useful purpose if no detectable leakage exists. Non-performance of the VT-2 visual examTnation would benefit ALARA vithout impacting on component reliability.
.. N .
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PY-CEI/NRR-1208 L-Attachment l' ,
Page 19 of 19 "
Perry Nuclear Power Plant RELIEF REQUEST #PT-003
? age 3 of 3 V. Alternate Examination 1
~ Quantifying leakage rates as n_9 detectable leakage utilizing test instrumente-(calibrated equipmeit), rather than a VT-2 valkdown, is used as an alternative technique. ,
i Pen. No.- - Designation P&ID No.
P107 RHR Relief Line to Suppression Pool D-302-641, 642, 705, 971 P108. Condensate Supply D-302-102 P109 Containment Leak Test D-302-811 P111 - Condensate Return D-302-102 P114 Containment'. Vacuum Relief P115 D-912-606 'j RCIC Turbine Exhaust Vacuum Relief- D-302-631, 641, l
~
642, 643 1 P117 ' Nitrogen Supply to CRD's D-302-950 P118 RHR Heat Exchanger Vent D-302-641, 642 .l
,P119 Containment Leak Rate D-302-811
.P120 Containment Leak Rate D-302-811 P201 Dryvell Atmosphere Radiation Monitor Line D-806-004 j
.P203 Fuel Pool Cooling Supply D-302-651 P208 :
Containment Vacuum Relief D-912-606 j P210 Carbon Dioxide To Fire Protection System: D-914-005- i P301 Puel-Pool Cooling Return D-302-651 P302 Backup Hydrogen Purge System
~
d D-302-831 _)
-P305 Lover Personnel ~ Airlock D-302-761- ?!
P309 Demineralized Vster P312 Upper Personnel airlock D-302-713 D-302-761' i
-4 P317 Containment Atmosphere Radiation Monitor Line D-806-007.
P317 Containment Leak Rate
]
D-302-811 P318 Post LOCA Hydrogen-Analyzer Line D-302-431, 832 P319 !
. Containment Leak Rate D-302-811 P406 Fire Protection Vater D-914-003 P413 Post Accident Sampling .
.D-302-431 j P417 Egiupment Drain Sump to Radvaste D-302-739' !
P418 Floor Drain Sump'to Radvaste D-302-740
.P420~ l Backvash Tank to Radvaste D-302-/37 i
'P424 RUCU to Hain Condenser and Radvaste D-302-672 i'
'P428 Containment Vacuum Relief D-912-606 P429 RHR Relief Line to Suppression Pool D-302-431, 642, 643 P431 RHR Heat Exchanger Vent D-302-642, 643 P436 Containment Vacuum Relief D-912-606 V313- Purge Supply D-912-604 .
V314- Purge Exhaust D-912-604 I
( m ,
PY-CEI/NRR-1208 L Attachment 2 '
Page 1 of 1 I
Vithdrawal of Inservice Relief Requests !R416 and IR-017 CEI has determined it necessary to withdrav/ delete N rn < M ief Requests
-IR-016 and IR-017 submitted to the NRC by letter PY;CBI/ W M 'JL on November
'17, 1989. Discussion of the-relief requests and the reauns tor their withdrawal are as follows:
Relief Request IR-016 Inservice Relief Request IR-016 was submitted to request relief from 100%
volumetric examination of the reactor head spray nozzle to vessel veld L (IB13-N8-KA) and nozzle inner radius (1-B13-N8-IR). The volumetric j examinations are required by ASHE XI, Examination Category B-D, Items No.'s B3.90 and B3.100 respectively. As reported in Preservice Relief Request #1, l l' the exams are limited by the close proximity of the adjacent N-7 nozzle.
Prior to Perry's first refuel, the NRC requested that Inservice Relief Requests, for known limitations, be submitted for the first interval, l Inservice Relief Request IR-001, submitted to the NRC by letter PY-CEI/NRR-0919L, listed the head spray nozzle exams on page 8 of 9 of the l relief request. The head spray nozzle exams were scheduled for, and .I performed, during Perry's first refueling outage. Following the outage, not l
realizing that relief had already been requested, Relief Request IR-016 was :
i-
-prepared in error. It should also be noted that the completion percentage i I
L reported for the inner radius exam in IR-016 (83%) was calculated in error and L the completie percentage reported in IR-001 (94%) is correct. ;
l-Relief Request ';R-017
- Relief Request IR-017 was prepared in error to report limited Augmented IGSCC examination of 4 stainless steel velds (1B13-N9A-KC, 1B13-N9B-KC, 1B33-0008- l' and 1B33-0107). All four velds have joint geometry which precludes two sided l
ultrasonic examinations and must therefore bm axamined from one-side only.
Generic Letter 88-01 requires that the examinations performed on these velds p should comply with he ASME Code, Section XI and that the detailed procedure, E equipment and examination personnel shall be-qualified in accordance with the NDE Coordination Plan implemented at the EPRI.NDE Center. The Code requires 2 directional angle beam coverage of the veld required volume (inner 1/3T). The exams performed achieved the required coverage by utilizing 5/8ths-V ,
calibrations and extrapolating the DAC to cover the examination volume. The equipment, procedure (all essential variables) and personnel were all qualified in accordance with NDE Coordination Plan at the EPRI NDE Center. In o' addition to the procedures / techniques required by the code and employed by EPRI at thg NDE Center, Perry procedures call for supplemental examination angles (70 ) and a half-V examination from both sides of the veld. The L limitation reported in Relief Request IR-017 was thus only a site specific requirement. No relief fro:n Code requirements is necessary and the augmented requirements of Generic Letter 88-01 are being met.
t '. ,
d PY-CEI/NRR-1208 L I Attachment 3 Page 1 of 2' Clarification of Pre-Service Relief Request 911 CEI has-also determined the need te Snylfy the relief requested in Preservice Relief Request'til (and subsequently resubmitted as Inservice Relief Request
- IR-009) with regard to the staff's (NRC) evaluation in Appendix 0 of the Perry SSER No. 7. Relief from 100% surface examination of the Code required examination area was requested for.the CRD housing flange velds. The surface examinations are required by ASME XI, Examination Category B-0, Item No.
B14.'10. The relief is necessary as 15% of the surface examination area of each housing to flange veld is inaccessible due to obstruction by the control (inlet and withdrav) lines'(sec Attachment 3, page.2 of 2). The control lines closely parallel the CRD housing and are velded into the CRD flanges. The staff concluded that " removal of the installed CRD support structure" solely for the purpose of performing the required surface examination vas not necessary, but should the CRDH's be " disassembled" fc
- Inserv.4.ce repair or maintenance, such that the subject velds- are accessible, t.se surface examinations would be required to be performed at that time. The enn mechanisms are routinely disassembled for in-service repairJor raintenance, but-the disassembly does not provide access to the portions of the CRD housing to flange veld obstructed by the control lines. The Staff approval of the Inservice Relief Request #1R-009 transmitted by letter dated April 25, 1990 did not specifically repeat this requirement. However, we commit that in the event the control lines vould be removed for repair or maintenance, the
'regrited examination vill be performed.
l ii NJC/ CODED /3678 1
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d
, *, , PY-CEI/NRR-1208 L Attachment 3 Page 2 of 2 l
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