ML20140E861
| ML20140E861 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 01/29/1986 |
| From: | Cooney M PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | Bernero R Office of Nuclear Reactor Regulation |
| References | |
| CON-#186-023, CON-#186-23 OL, NUDOCS 8602040105 | |
| Download: ML20140E861 (7) | |
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PHILADELPHIA ELECTRIC COMPANY 23O1 MARKET STREET P.O. BOX 8699 PHILADELPHIA, PA.19101 (2 s) e41-so20
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January 29, 1986 Docket No. 50-352 Mr. Robert Bernero, Director Division of Boiling Water Reactor Licensing U.S. Nuclear Regulatory Commission Washington, D.C.
20555
Dear Mr. Bernero:
The following information is provided in response to a Request for Additional Information (RAI) from Mr. R. E. Martin, Limerick Project Manager, of your staff, in support of a December 18, 1985 Request for Amendment to the Limerick Operating License and Temporary Exemption to the requirements of Appendix J to 10 CFR 50.
This request was directed towards supplying information relative to industry experience with valves similar to those which were the subject of the Amendment Request.
In order to support this RAI, a multi-faceted program has been undertaken which includes the following: 1) Review of Nuclear Plant Reliability Data systems; 2) Contact with other utilities identified as having similar valves; 3) Contact with valve manufacturers of the specific valves; and 4) Review of general experience with testing of similar valves at Peach Bottom Atomic Power Station (PBAPS ).
Table 1 (attached) addresses item 1 above.
Items 2 and 3 remain under investigation.
In response to item 4, general experience with similar valves at PBAPS indicates that valve leakage appears to be related to type of service and time in service.
Valves which are used in non-modulating applications, such as those which are the subject of this amendment request, tend not to have problems meeting leakage criteria.
Table 2 (attached) is a compilation of information regarding the valves for which temporary relief of the testing requirement is sought.
EB (LIAW)
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PS!! (L. HilLMAN) sh2040105 96012'?ADOCK 05000352
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... O Mr. Robert Bernero January 29, 1986 Page 2 The information gathered thus far has revealed nothing which would alter or affect the conclusions contained within our application.
Should you have any questions or require additional information, please do not hesitate to contact us.
Very truly yours,
/
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Attachments cc:
Dr. Thomas E. Murley, Administrator, Region I, USNRC E.M.
Kelly, Senior Resident Site Inspector See Attached Service List
Table 1 - Explanation Results of review of industry experience conducted through Nuclear Plant Reliability Data System Columns l _2, 3, 4 t
Manuf acturer, Model Number, Size and Type of valves which are the subject of the amendment request.
f Column 5 - Similar Number Identified Number of valves identified upon interrogation of NPRD data base.
Search was based upon manufacturer, type and size range (e.g. Velan, gate, 2"-6").
Computer generated listing was manually sorted to identify similar model numbers.
If no similar model numbers were identified, the number reported represents the numbers of all valves of same manufacturer, type and specific size.
Column 6_
NP RD failure reports were obtained for all valves identified and reported in Column 5.
These reports were reviewed and those failures which were relevant to leakage rates and isolation function are tabulated.
It is notable that the reported failures concern valves which have been in service for significant periods and were reported to NP RD as " wear-out".
Column,7 Identifies those totals which are reported for all valves of same size when similar model numbers could not be identified.
TABLE 1
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i NPRDS REVIEW OF SIMIIAR VALVES t
SIMIIAR MEANINEUL NGEER FAIIURES
. MANUFAC7URER MODEL SIZE TYPE IDENTIFIED REPORED cot @ENTS Velan B12-000548-02WN 3"
Gate 30 0
B10-000548-0ZvN Crane Cat. {47XUF 8"
Gate 198 0
Rockell 1-3624F316 IMP 1"
Globe 492 28 1 1/2-3624F316IINT 1 1/2" Globe Atvcxx3 & bbrrill 13673-02-03-05-06 12" CK 0(61*)
6*
- All Models.
j 13673-01-04 Anchor / Darling SJO-2171-52 8"
Gate 0(337*)
4*
- All Models.
SJO-2159-15 6"
Globe 0(46*)
1*
- All Models.
SJO-2159-16 SJO-5348-06 l
SJO-5348-07 12" Gate 0 (226*)
1*
- All bbdels.
t Borg Warner Part No. 77940 1"
CK 0(21*)
O Circle Seal NV02-14 1"
CK 0(14*)
2*
- All Models.
TABLE 2 Penstration Nu=ber Valve Numbers Test Frequency of Previous Process Valve end Description (Size - Inches)
Medium Valve Operation Test Results Fluid
}fanufacturer Type Nodel Number X-3D HV-59-151B (1)
N.O. Stroked Quart 7.54 SCCM PCIC or Rockwell Globe 1-3624 F3161JE Instrumest Cas 59-1112 (1)
Air Check Stroked Refuel 1.45 SCCM Instrument Circle Seal check NV02-14 Supply Air X-13A HV-51-1F050A (12)
Air /
Check Streked Refuel 0.1 CPM
- Reactor Atwood & Morrill Check 13673-01-04
'A' RHR Shutdown HV-51-151A (1.5)
Water N.C. Not Stroked 0.1 CPM
- Demineralized Water Rockwell Globe 1 1/2-3624F316 1.MMI Cooling Return X-13B HV-51-IF050B (12)
Air /
Check Stroked Refuel 0.0 CPM
- Reactor Atwood & Morrill Check 13673 01 04 down EV-51-151B (15)
Water N.C. Not Stroked 0.0 CPM Demineralized Rockwell Clobe 1 1/2-3624F316 lyJE Water X-14 HV-44-IF001 (6)
Air N.O. Stroked Quart 24.0 SCCM Reactor Anchor / Darling Clobe
$30-2159-15 Reactor Water HV-44-IF004 (6)
N.O. Stroked Quart 485.75 SCCM Demineralized Anchor / Darling Globe SJ0-2159-16 Cleanup Supply Water X-23 HV-13-106 (4)
N.O. Stroked Refuel 121.8 SCCM React. Encl.
Velan Cate B12-00054B-02W Reactor Enclosure HV-13-108 (3)
Air N.O. Stroled Refuel 23.25 SCCM*
Cooling Water Velan Cate B10-00054B-02W Cooling Supply HV-13-109 (3)
N.C. Not Stroked 23'.25 SCCM*
Demin. Water Velan Cate B10-000548-02W X-24 HV-13-107 (4)
N.O. Stroked Refuel 5.2 SCCM React. Incl.
Velan Cate 312-00054B-02W Reactor Enclosure HV-13-110 (3)
Air N.C. Not Stroked 3.6 SCCM*
Cooling Water Velan Cate B10-00054B-02W Cooling Return HV-13-111 (3)
N.O. Stroked Refuel 3.6 SCCM*
Demin. Water Velan Cate B10-00054B-02W X-45A HV-51-1F041A (12)
Air /,
Check Stroked Refuel 0.0198 CPM
- Suppression Atwood & Morrill Check 13673-02-03-05-06
'A' RER LPCI HV-51-1F017A (12)
Water N.C. Stroked Refuel 84.75 SCCM Pool Water Anchor / Darling Cate SJ0-5348-07 HV-51-142A (1.5)
N.C. Not Stroked 0.0198 CPM
- Rockwell Clobe 1-3624F3161FJE X-45C HV-51-IF041C (12)
Air /
Check Stroked Refuel 0.002 CPM
- Suppression Atwood & Morrill Check 13673-02-03-05-06
'C' RER LPCI HV-51-lF017C (12)
Wster N.C. Stroked Refuel 148. SCCM Pool Water Anchor / Darling Cate SJ0-5348-07 HV-51-142C (1.5)
N.C. Not Stroked 0.002 CFM
- Rockwell Globe 1-3624F316LFJE 1
X-45D HV-51-IF041D (12)
Air /
Check Stroked Refuel 0.0828 CPM
- Suppression Atwood & Morrill Check 13673-02-03-05-06
'D' RER LPCI HV-51-IF017D (12)
Water N.C. Stroked Refuel 976.8 SCCM Pool Water Anchor / Darling Cate SJ0-5348-07 HV-51-142D (1.5)
N.C. Not Stroked 0.0828 CPM
- Rockvell Globe 1-3624F3161J02 X-53 HV-87-120A (8)
N.O. Stroked Quart 170.5 SCCf*
Demineralized Crane Cate Cat. No. 47XUF Water Cran Cate Cat. No. 47XUF Dryvell Chilled HV-87-125A (8)
Air N.C. Stroked Qutzt 170.5 SCCM 32.25 SCCM Anchor [ Darling Cate 5J0-2171-52 Water Supply HV-87-128 (8)
N.O. Stroked Quart
. - - _ - -... - -.. - - -. ~ _. - - - - - -...
.. - - ~ - -.. -.. - - - - - - - - -.,. -
- ~....
i 3
TABLE 2 s
1 Fenstration Number Valve Numbers Test Frequency of Frevious Process Valve end rescription (Size - Inches)
Medium Valve Operation Test Results Fluid Manufacturer Type Model N aber 4
i X-54 HV-87-121A (8)
N.O. Stroked Quart 556.2 SCCM*
Crane Cate Cat. No. 47XUF
}
Drywell Chilled hT-87-124A (8)
Air N.C. Stroked Quart 556.2 SCCM
- Demineralized Crane Cate Cat. No. '47XUF t
j Water Return HV-87-129 (8)
N.O. Stroked Quart 97.2 SCCM Water Anchor / Darling Cate SJ0-2171-52 l
t X-55 HV-87-1205 (8)
N.O. Stroked Quart 656.5 SCCM*
C e
Cate Cat. No. 47XUF f
)
Dryvs11 Chilled HV-87-122 (B)
Air N.C. Stroked Quart 11.4 SCCM Demineralized AnchNfDarling Cate SJ0-2171-52' t
l Water Supply HV-87-1255 (8)
N.C. Stroked Quart 656.5 SCCu*
Water Crane Cate Cat. No. 47XUF L
f l
X-56 HV-87-121B (8)
N.O. Stroked yuart Jul.t> b w Crane Cate Cat. No. 47XUF Drywell Chilled HV-87-123 (8)
Air N.C. Stroked Quart 35.5 SCCM Demineralized Anchor / Darling Cate SJ0-2171-52
}
Water Return HV-87-124B (8)
N.C. Stroked Quart 302.6 SCCM*
Water' Crane Cate Cat. No. 47XUF X-613 CRD or BORC Warner Check Fart No. 77940
'B' Recire. Pmp 43-1004B (1)
Air Check Stroked Refuel 75.9 SCCM Reactor i
Seal Purge Demin. Water I.
t I
X-205A Suppression i
l Suppression HV-51-1F027A (6)
Air N.C. Stroked Quart.
2.25 SCCM Fool Water Anchor / Darling Clobe SJ0-5348-06 or Air Fool Spray N.O. Normally Open
- Valves tested
{
j N.C. Normally Closed together.
l Leakage assign-i ed to both.
l!
Current total of tne C r
i test 22.000 SCCM e
i I
.l 9,
L I
I 1
1 i
cc:
Troy B. Conner, Jr., Esq.
Ann P. Hodgdon, Esq.
Mr. Frank R. Romano Mr. Robert L. Anthony Ms. Phyllis Zitzer Charles W. Elliott, Esq.
Zori G. Ferkin, Esq.
Mr. Thomas Gerusky Director, Penna. Emergency Management Agency Angus Love, Esq.
David Wersan, Esq.
Robert J. Sugarman, Esq.
Kathryn S. Lewis, Esq.
Spence W. Perry, Esq.
Jay M. Gutierrez, Esq.
Atomic Safety & Licensing Appeal Board Atomic Safety & Licensing Board Panel Docket & Service Section (3 Copies)
E. M. Kelly Timothy R. S. Campbell September, 1985 k
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