Letter Sequence Approval |
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Results
Other: ML20133J280, ML20137H873, ML20137S539, ML20137U023, ML20138L219, ML20141F643, ML20151X932, ML20151Z255, ML20199D831, ML20203E089, ML20206J086, ML20210K261
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MONTHYEARIR 05000348/19850361985-09-19019 September 1985 Insp Repts 50-348/85-36 & 50-364/85-36 on 850811-0910.No Violations or Deviations Noted.Major Areas Inspected: Licensee Action on Previous Enforcement Matters,Monthly Surveillance Observations,Monthly Maint Observation & LERs Project stage: Request ML20133J2801985-10-14014 October 1985 Forwards Three Addl Requests for Relief from Inservice Insp Program for ASME Code Class 1,2 & 3 Components Re Reactor Vessel Flange Ligaments & Visual Exam of Reactor Coolant Pump Casing Pressure Boundary Surfaces.Fee Paid Project stage: Other ML20138L2191985-10-21021 October 1985 Requests Assistance in Reviewing Encl Util 850919 Proposed Administrative Tech Spec Change,Implementing Listed Mgt Changes.Ser & SALP Input Requested by 851031 Project stage: Other ML20137S6411985-11-17017 November 1985 Proposed Changes to Tech Spec 4.2.4.2 & Action 2.d of Table 3.3-1 to Allow Full Core Flux Map for Verifying Indicated Quadrant Power Tilt Ratio When One ex-core Power Range Detector Channel Inoperable Project stage: Request ML20137H8371985-11-22022 November 1985 Application for Amends to Licenses NPF-2 & NPF-8,revising Note 9 of Tech Spec Table 4.3-1 to Require Clearing of Trip Signal Prior to P-9 Setpoint.Fee Paid Project stage: Request ML20137H8731985-11-22022 November 1985 Proposed Tech Spec Changes to Note 9 of Table 4.3-1, Requiring Clearing of Trip Signal Prior to P-9 Setpoint Project stage: Other ML20137U0231985-11-27027 November 1985 Proposed Tech Spec Pages 3/4 2-8,3/4 2-10 & B3/4 2-4, Deleting Rod Bow Penalty Project stage: Other ML20137K9071985-11-27027 November 1985 Forwards Summary of Activities Conducted Since 841130 Submittal & Schedule for Completing Remainder of Emergency Response Capability Integrated Implementation Plan Items. W/One Oversize Graphical Presentation of Plan & Schedule Project stage: Request ML20137U0111985-11-27027 November 1985 Application for Amends to Licenses NPF-2 & NPF-8,deleting Rod Bow Penalty from Tech Specs.Fee Paid Project stage: Request ML20137S5391985-11-27027 November 1985 Proposed Tech Spec Changes,Eliminating Requirement to Shut Down Plant If Coolant Iodine Activity Above 1 Uci/G for Greater than 800 H in 12-month Period,Per Generic Ltr 85-19 Project stage: Other ML20137S5211985-11-27027 November 1985 Application for Amends to Licenses NPF-2 & NPF-8,eliminating Tech Spec Requirement to Shut Down Plant If Coolant Iodine Activity Above 1 Uci/G for Greater than 800 H Period in 12 Months,Per Generic Ltr 85-19.Fee Paid Project stage: Request ML20137S6241985-11-27027 November 1985 Application for Amends to Licenses NPF-2 & NPF-8 to Permit Full Core Flux Map for Verifying Indicated Quadrant Power Tilt Ratio When One ex-core Power Range Detector Channel Inoperable Project stage: Request ML20136H6711985-12-27027 December 1985 Forwards Safety Evaluation Granting Util 851014 Request for Exemption from Section XI Requirements Re Reactor Vessel Flange Ligaments & Insp of Internal Pressure Boundary Surfaces & Flange Bolts Project stage: Approval ML20136H6821985-12-27027 December 1985 Safety Evaluation Granting Relief from Certain Inservice Testing/Insp Requirements Re Reactor Vessel Flange Ligaments,Reactor Coolant Pump Casing Internal Surfaces & Flange Bolts Project stage: Approval ML20151X9631986-01-27027 January 1986 Safety Evaluation Supporting Amends 60 & 51 to Licenses NPF-2 & NPF-8,respectively Project stage: Approval ML20151X9321986-01-27027 January 1986 Amends 60 & 51 to Licenses NPF-2 & NPF-8,respectively, Revising Administrative Controls Section of Tech Specs to Reflect Titles of Onsite & Offsite Licensee Mgt Project stage: Other ML20151Z2551986-02-0707 February 1986 Forwards Proposed Schedules for Completion of License Amend Requests & Other NRC-related Submittals Project stage: Other ML20199D8311986-03-14014 March 1986 Amends 61 & 52 to Licenses NPF-2 & NPF-8,respectively, Revising Tech Spec Surveillance Requirements for Quadrant Power Tilt Ratio,Allowing Use of Full Core Flux Map Using Two Sets of Four Symmetric Thimble Locations Project stage: Other ML20199D8431986-03-14014 March 1986 Safety Evaluation Supporting Amends 61 & 52 to Licenses NPF-2 & NPF-8,respectively Project stage: Approval ML20141F6431986-04-11011 April 1986 Forwards Amended Significant Hazards Evaluation & Revised Tech Spec Pages Removing Rod Bow Penalty from Nuclear Enthalpy Hot Channel Factor,Per Util 851127 Request to Amend Licenses NPF-2 & NPF-8 Project stage: Other ML20203E0891986-04-15015 April 1986 Amends 62 & 53 to Licenses NPF-2 & NPF-8,respectively, Revising Tech Spec Table 4.3-1 Re Reactor Trip Sys Instrumentation Surveillance Requirements Project stage: Other ML20203E0971986-04-15015 April 1986 Safety Evaluation Supporting Amends 62 & 53 to Licenses NPF-2 & NPF-8,respectively Project stage: Approval ML20210K2611986-04-16016 April 1986 Amend 63 & 54 to Licenses NPF-2 & NPF-8,respectively, Deleting Tech Spec 3.4.9 Action Statement a Requiring Plant Shutdown When Coolant Activity Exceeds Cumulative Spiking Limit Project stage: Other ML20210K2731986-04-16016 April 1986 Safety Evaluation Supporting Amends 63 & 54 to Licenses NPF-2 & NPF-8,respectively Project stage: Approval ML20206J0921986-06-16016 June 1986 Safety Evaluation Supporting Amends 64 & 57 to Licenses NPF-2 & NPF-8,respectively Project stage: Approval ML20206J0861986-06-16016 June 1986 Amends 64 & 57 to Licenses NPF-2 & NPF-8,respectively, Modifying Tech Spec 3.2.3 to Delete Rod Bow Penalty & Deleting Tech Spec Figure 3.2-3 Project stage: Other 1985-09-19
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December 27, 1985 1
7 Docket Nos. 50-348 DISTRIBUTION j
and 50-364
['.poetetluer EJordan NRC PDR BGrimes Local PDR JPartlow PAD-2 rdg TBarnhart(8) i 3
HDenton ACRS (10)
Mr. R. P. Mcdonald DEisenhut OPA Senior Vice President HThompson SECY j
Alabama Power Company ORAS CMiles, LFMB i
Post Office Box 2641 CParrish Gray File i-Birmingham, Alabama 35291 EReeves(.d
- 8. TiA AorLM OELD
- 6. WNEidN
Dear Mr. Mcdonald:
I
SUBJECT:
RELIEF FROM ASME SECTION XI INSPECTION REQUIREMENTS FOR CERTAIN REACTOR VESSEL FLANGE LIGAMENTS; AND REACTOR COOLANT PUMP CASING INTERNAL SURFACES AND FLANGE BOLTS - JOSEPH M. FARLEY NUCLEAR l
PLANT UNITS 1 AND 2 i
By letter dated October 14, 1985, you requested relief from certain test requirements of ASME Code Section XI for Farley Nuclear Plant, Units 1 and 2.
Your request relates to testing by volumetric inspection of nine of the 58 ligaments between stud holes of the reactor vessel flange and inspection of the internal pressure boundary surfaces and flange bolts requiring disassembly 5
i of the reactor coolant pump.
j We previously granted certain reliefs which you requested pursuant to 10 CFR j
50.55a(g) in our letters dated December 7, 1979, August 24, 1983, February 10 and March 30, 1984 (one-time relief) and January 10, 1985. This request, also i
{
pursuant to 10 CFR 50.55a(g), is for three additional reliefs from certain
[
i ASME Code requirements as noted above.
l i
The enclosed Safety Evaluation delineates the three items for which additional i
relief is granted and for which alternate testing is authorized. The staff t
i has determined that where stated the ASME Code requirements are impractical, y
}
the alternative methods to be performed will provide adequate assurance of i
i the structural integrity of the components evaluated, and pursuant to
[
{
10 CFR 50.55a(g)(6)(1) the granting of this relief is authorized by law and
}
l will not endanger life or property of the common defense and security, and i
i is otherwise in the public interest.
In making this determination, we have given due consideration of the burden that could result if these requirements l
were imposed on your facility.
l I
r 4
\\
I l
i
Mr. R. P. Mcdonald A copy of our Safety Evaluation for granting of relief is enclosed.
Sincerely, edglaalt!gned1:/
L. S. Rubcastein Lester S. Rubenstein, Director PWR Project Directorate #2 Division of PWR Licensing-A
Enclosure:
As stated cc w/ enclosure:
See next page 1fE CParrish g es:8N BSD-2 o t ha V
u:eeD-8 EReeves:he LRubenstei filean /
12/ \\V85 12/l]/85 12/l(/85 12/>6/85
Mr. R. P. Mcdonald Alabama Power Company Joseph M. Farley Nuclear Plant CC:
Mr. W. O. Whitt D. Biard MacGuineas. Esquire Executive Vice President Volpe, Boskey and Lyons Alabama Power Company 918 16th Street, N.W.
Post Office Box 2641 Washington, DC 20006 Birmingham, Alabama 35291 Charles R. Lowman Mr. Louis B. Long, General Manager Alabama Electric Corporation Southern Company Services Inc.
Post Office Box 550 i
Post Office Box 2625 Andalusia, Alabama 36420 Birmingham, Alabama 35202 Chairman Regional Administrator, Region II Houston County Commission U.S. Nuclear Regulatory Commission Dothan, Alabama 36301 101 Marietta Street, Suite 2900 Atlanta, Georgia 30303 George F. Trowbridge, Esquire Shaw, Pittman, Potts and Trowbriage Ira L. Myers, M.D.
/
1800 M Street, N.W.
State Health Officer Washington, DC 20036 State Department of Public Health State Office Building Montgomery Alabama 36130 Robert A. Buettner, Esquire Balch, Bingham, Baker Hawthorne, Mr. J. D. Woodard Williams and Ward General Manager - Nuclear Plant Post Office Box 306 Post Office Box 470 Birmingham, AlaL:ma 35201 Ashford, Alabama 36312 Resident Inspector U.S. Nuclear Regulatory Commission Post Office Box 24 - Route 2 Columbia, Alabama 36319 State Department of Public Health ATTN: State Health Officer State Office Building Montgomery, Alabama 36104 l
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