ML17158A308
| ML17158A308 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna |
| Issue date: | 05/25/1994 |
| From: | Poslusny C Office of Nuclear Reactor Regulation |
| To: | Byram R PENNSYLVANIA POWER & LIGHT CO. |
| References | |
| IEB-93-003, IEB-93-3, TAC-M86912, TAC-M86913, NUDOCS 9406030107 | |
| Download: ML17158A308 (5) | |
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Docket Nos.
50-387 and 50-388 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 May 25, 1994 Mr. Robert G.
Byram Senior Vice President-Nuclear Pennsylvania Power and Light Company 2 North Ninth Street Allentown, Pennsylvania 18101
Dear Mr. Byram:
SUBJECT:
RESPONSE
TO NRC BULLETIN 93-03, "REMLIIJTION OF ISSUES RELATED TO REACTOR VESSEL WATER LEVEL INSTRUIIIEMTiATI,ION IN BWRS" (TAC NOS.
M86912 AND M86913)
We acknowledge receipt of your responses, dated July 29, 1993 and February 17, 1994 to NRC Bulletin (NRCB) 93-03.
The NRCB Max issued May 28, 1993, to all holders of operating licenses or construction, permits for boiling water reactors (BWRs) with the exception of Millstene II and Big Rock Point.
The NRCB requested licensees to take short-term caIItpensatory measures within 15 days of the NRCB to ensure that. operators we~e abl:e to identify and mitigate to implement hardware modifications at the fiIrsi cold shutdown after July 30, 1993, to ensure the level instrumentation system idesign would be of high functional reliability for long-term operation Your July 29, 1993 response stated that you impel,emented appropriate short-term compensatory measures.
These were found to he acceptable to the staff.
Subsequently you installed backfill systems tto purge the non-condensible gases from the reference legs on each Susquehanna Unit Specifically, the modifications were installed in March 1993 fer Ionit 1 and in February 1994 for Unit 2.
Your letter of February 17, 1994 prove dad the report which confirmed completion and implementation of the required Imodifications.
The dates of installation were consistent with NRCB 93-03.
'The staff understands that the modifications did not involve an unreviewed saIfeky question and were implemented under 10 CFR 50.59.
.Based on the information provided in your Febnuary 17, 1994 letter, we consider your response to NRCB 93-03 acceptabie..
Please retain records related to your actions taken in response to 5hIis NRCB for possible future inspection by the NRC staff.
9406030107 940525, PDR ADQCK 05000387 P
PDR)
<C Hr. Robert G.
Byram Nay 25, 1994 In a letter dated January 19,
- 1994, PPItL described a passive condensing chamber vent modification which was being developed and tested for installation on the Susquehanna units.
The staff understands that the modification to install this passive alternative vessel level measurement system is being implemented under 10 CFR 50.59.
An infor'mation meeting is being set up for PPEL to present design and testing information for this system to the staff in June 1994.
This modification is being installed on Unit 2 during the current outage and will be installed on Unit 1 at the next outage.
L The NRC staff issued NRC Information Notice (IN) 93-89, "Potential Problems With BWR Level Instrumentation Backfill Modifications."
The staff is still reviewing the concerns identified in this IN, and any possible actions will be addressed separately from this TAC.
Sincerely,
/s/
cc:
See next page Chester
- Poslusny, Project Manager Project Directorate I-2 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation DISTRIBUTION:
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Mr. Robert G.
Byram
~ihy 25, 1994 In a letter dated January 19,
- 1994, PPKL described a passive condensing chamber vent modification which was being developed and tested for installation on the Susquehanna units.
The staff understands that the modification to install this passive alternative vessel level measurement system is being implemented under 10 CFR 50.59.
An.information meeting is being set up for PPKL to present design and testing information for this system to the staff in June 1994.
This modification is being installed on Unit 2 during the current outage and will be installed on Unit 1 at the next outage.
The NRC staff issued NRC Information Notice (IN) 93-89, "Potential Problems With BWR Level Instrumentation Backfill Modifications."
The staff is still reviewing the concerns identified in this IN, and any possible actions will be addressed separately from this TAC.
Sincerely, Chester
- Poslusny, roject Manager Project Directorate l-2 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation cc:
See next page
~ l Mr. Robert G.
Byram Pennsylvania Power
& Light Company Susquehanna Steam Electric Station, Units
- 3. 2 2 CC:
Jay Silberg, Esq.
- Shaw, Pittman, Potts 5 Trowbridge 2300 N Street N.W.
Washington, D.C..
20037 Bryan A. Snapp, Esq.
Assistant Corporate Counsel Pennsylvania Power 8 Light Company 2 North Ninth Street Allentown, Pennsylvania 18101 Mr. J.
M. Kenny Licensing Group Supervisor Pennsylvania Power E Light Company 2 North Ninth Street Allentown, Pennsylvania 18101 Mr. Scott Barber Senior Resident Inspector U. S. Nuclear Regulatory Commission P.O.
Box 35 Berwick, Pennsylvania 18603-0035 Mr. William P. Dornsife, Director Bureau of Radiation Protection Pennsylvania Department of Environmental Resources P. 0.
Box 8469 Harrisburg, Pennsylvania 17105-8469 Mr. Jesse C. Tilton, III Allegheny Elec. Cooperative, Inc.
212 Locust Street P.O.
Box 1266
'arrisburg, Pennsylvania 17108-1266 t
Regionall,Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allandale Road King of 'Prussia, Pennsylvania 19406 Mr. Harotl,d C. Stanley Vice Pres%dent-Nuclear Operations Susquehanna Steam Electric Station Pennsylvania Power and Light Company Box 467 Berwick, )Pennsylvania 18603 Mr. Herbent 9. Woodeshick Speci,al,0ftice of the President Pennsyl'vanria Power and Light Company Rural Quite i, Box 1797 Berwick fP+nnsylvania 18603 George T.. cojones Vice PresMent-Nuclear Engineering Pennsyl! err'ia Power and Light Company 2 Nor& iNiinth Street Al1 eniawn fPennsyl vani a 18101