ML20043B485
| ML20043B485 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 05/23/1990 |
| From: | Clark R Office of Nuclear Reactor Regulation |
| To: | Hunger G PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| References | |
| IEB-89-002, IEB-89-2, TAC-74271, TAC-74272, NUDOCS 9005300092 | |
| Download: ML20043B485 (3) | |
Text
o May 23, 1990
' Docket Hos. 50-352 and 50-353 DISTRIBUTION:
Mr. George A. Hunger, Jr.
5553FTITiin 0GC Director-Licensing, MC 5-2A-5
'NRC/ Local PORs*
EJordan Philadelphia Electric Company PDI-2 Reading ACRS(10)
Nuclear tiroup Headquarters SYarga PDI-2 Gray File Correspondence Control Desk BBoger HRood PDV Post Office Box No. 195 M0'Brien TMcLellan, EMCB Wayne, Pennsylvania 190B7-0195 kJClark DSe11ers, EMCB RBlough, RI LDoerflein, RI
Dear Mr. Hunger:
SUBJECT:
NRC BULLETIN 89-02: STRESS CORROSION CRACKING OF HIGH-ilARDNESS TYPE 410 STAINLESS STEEL INTERNAL PRELOADED BOLTING IN ANCHOR DARLING MODEL S350W SWING CHECK VALVES OR VALVES OF SIMILAR DESIGN (MPA X 902), LIMERICK GENERATING STATION, UNITS 1 AND 2 (TAC N05. 74271 AND 74272)
The subject Bulletin, issued July 19,19B9, requested licensees and aaplicants to identify, disassemble and inspect certain types of swing c1eck valves which may contain Type 410 stainless steel (SS) bolting material.
If the Type 410 $$ bolting material is of sufficiently high hardnessthatitissusceptibletostresscorrosioncracking(SCC),or has failed, addressees were requested to take appropriate actions.
Your response of January 16, 1990 reported that you had previously reviewed safety-related systems for Limerick, Units 1 and 2, as a result of NRC Information Notice No. 88-05 to determine if check valves as described in the Information Notice were installed at Limerick.
Your review revealed four Anchor Darling valves, containing ASTM A 103 Grade B6 Type 410 SS~ stud material had been installed in one system. The Type 410 SS retaining block studs were removed and visually inspec W and no signs c,f cracking or corrosion were evident. However, the s% were replaced with AISI designation Type 17-4 PH SS as recommendeo ey the valve manufacturer. This work was completed by August 29, 1989.
Your response acceptably completes all of the rquested actions in Bulletin 89-02, including the reporting reoairements. For purposes of our Safety Issues Management System (SIMS), implementation is considered complete as of January 16, 1990, the date of your response. The NRC accession number on your letter is 9001250444 This issue is considered closed for Limerick, Units 1 and 2.
l Sincerely, l
Original signed by Richard J. Clark Richard J. Clark, Project Manager Project Directorate I-2 9005300092 coos 23 Division of Reactor Projects - 1/11 ADOCK05cof$hs Office of Nuclear Peactor Regulation paa o
cc: See next page l
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May 23, 1990 i
-Docket Nos. 50-352 and 50-353 Mr. George A. Hunger, Jr.
Director-Licensing, MC 5-2A-5 Philadelphia Electric Company Nuclear Group Headquarters Correspondence Control Desk Post Office Box No. 195 Wayne, Pennsylvania 19087-0195 l
Dear Mr. Hunger:
SUBJECT:
NRC BULLETIN 89-02: STRESS CORROSION CRACKING OF HIGH-HARDNESS TYPE 410 STAINLESS STEEL INTERNAL PRELOADED BOLTING IN ANCHOR DARLING N0 DEL S350W SWING CHECK VALVES OR VALVES OF SIMILAR l
DESIGN (MPAX902),LIMERICKGENERATINGSTATION, UNITS 1AND2 (TAC NOS. 74271 AND 74272)
The subject Bulletin i 19, 1989, requested licensees and a)plicants to identify,ssued July disassemble and inspect certain t c1eck valves which may contain Type 410 stainless steel (ypes of swing SS) bolting material.
If the Type 410 SS bolting material is of sufficiently high hardness that it is susceptible to stress corrosion cracking (SCC), or has failed,' addressees were requested to take appropriate actions.
Your response of January 16, 1990 reported that you had previously reviewed safety-related systems for Limerick, Units 1 and 2, as a result of NRC Information Notice No. 88-05 to determine if check valves as described in the Information Notice were installed at Limerick.
Your
^
review revealed four Anchor Darling valves, containing ASTM A 193 Grade B6 Type 410 SS stud material had been installed in one system. The Type 410 SS retaining block studs were removed and visually inspected and no t
l signs of cracking or corrosion were evident. However, the studs were replaced with AISI designation Type 17-4 PH SS as recommended by the l
L valve manufacturer. This work was compicd by August 29, 1989.
1 l-Your response acceptably completes all of the requested actions in Bulletin 89-02, including the reporting re our Safety Issues Management System (SIMS)quirements. For purposes of
, implementation is considered complete as of January 16, 1990, the date of your response. The NRC accession number on your letter is 9001250444. This issue is considered closed for L*.erick, Units 1 and 2.
l
}j ds]
h ark,ProfectManager ect Di ectorate I-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation cc: See next page
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f i
Mr. George A. Hunger, Jr.
Limerick Generating Station Philadelphia Electric Company Units 1 & 2 1
1 i
Cc:
Troy B. Conner, Jr., Esquire Mr. Thomas Gerusky, Director Conner and Wetterhahn Bureau of Radiation Protection i
1747 Pennsylvania Ave., N.W.
PA Dept. of Environmental Resources I
. Washington, D. C.
20006 P. O. Box 2063 Harrisburg, Pennsylvania 17120 Mr. Rod Krich 52A-5 4
Philadelphia Electric Company Single r int of Contact o
955 Chesterbrook Boulevard P. O. Box 11880 Wayne, Pennsylvania 19087-5691 Harrisburg, Pennsylvania 17108-1880 J
Mr. Graham M. Leitch, Vice President Mr. Philip J. Duca limerick Generating Station Support Manager Post Office Box A Limerick Generating Station Sanatoga, Pennsylvania 19464 P. O. Box A Sanatoga, Pennsylvania 19464 Mr. Marty J. McCormick, Jr.
Plant Manager Mr. Garrett Edwards Limerick Generating Station Superintendent-Technical P.O. Box A Limerick Generating Station Sanatoga, Pennsylvania 19464 P. O. Box A Sanatoga. Pennsylvania 19464 Mr. Larry Doerflein U.S. Nuclear Regulatory Commission Mr. Gil J. Madsen Region 1 Regulatory Engineer 475 Allendale Road Limerick Generating Station King of Prussia, PA 19406 P. O. Box A Sanatoga Pennsylvania 19464 Mr. Thomas Kenny Senior Resident inspector US Nuclear Regulatory Commission P. O. Box 596 Pottstown, Pennsylvania 19464 fir. John Doering ProjectManager Limerick Generating Station P. O. Box A Sanatoga, Pennsylvania 19464 L
Mr. Larry Hopkins Superintendent-Operations i
Limerick Generating Station p
P. O. Box A Sanatoga, Pennsylvania 19464
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