ML20210P552
| ML20210P552 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 08/20/1997 |
| From: | Abney T TENNESSEE VALLEY AUTHORITY |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9708270224 | |
| Download: ML20210P552 (6) | |
Text
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knneuec vasey AutnonU$ iib 5[e'IS[$oo onma,, A%ama moa I
August 20, 1997
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U.S. Nuclear Regulatory Commission l
j ATTN:
Document Control Desk i
Washington, D.C.
20555 l
Gentlemen:
In the Matter of
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Docket Nos. 50-259 Tennessee Valley Authority
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50-260 50-296 i
BROWNS FERRY NUCLEAR PLANT (BFN) - UNITS 1, 2, AND RESPONSE TO REQUEST FOR INFORMATION - TECHNICAL SPECIFICATION (TS) -353R1 AND TS-353S1 - AVERAGE POWER RANGE MONITOR-ROD BLOCK MONITOR TECHNICAL SPECIFICATIONS (ARTS)
This letter responds to a verbal request from the NRC's Project Manager that TVA docket a review of the effects of a Notice of Nonconformance (NON) from an NRC inspection of General Electric (GE)' to the Rod Block Monitor (RBM) operability provisions in proposed TS-353R1 and TS-353Sl.
TS-353R1 (submitted March 6,-
1997) and TS-353S1 (April 11, 1997) support the planned adoption-of the ARTS improvements and Maximum Extended Load Line L' tit Analysis, as well as the installation of the Power Range scutron Monitoring System.
These changes are scheduled to be first implemented on Unit 2 Cycle 10 (October 1997).
4 The NRC Inspection Report, which was issued on June 11, 1997, involved the: inspection of the GE Nuclear Energy facility and the core reload analyses performed for various domestic Boiling Water Reactors licensees.
NON 99900003/97-01-01 from the inspection was associated with the failure of GE's supplemental reload licensing reports (SRLRs) to adequately consider RBM TS operability requirements when performing the Rod Withdrawal-Error (RWE) event analysis with regard to the 1 percent fuel plastic strain limits and mechanical overpower (MOP) limits.
The concern applies only to ARTS licensed plants.
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U.S. Nuclear Regulatory Commission Page 2 -
/uigus t 20, 1997 GE's corrective actions for the NON were submitted to NaC on June 10, 1997.
GE also notified TVA tha.t tne methodology for performing the cycle-specific core reload. analyses for the RWE had been modified to specifically address the concern by i
evalua ng the plastic strain and MOP limits in conjunction with the ARTS RBM TS operability requirements.
j Enclosed is a' letter dated August 13, 1997, from GE which summarizes the results of the cycle-specific RWE analysis for the i
Unit 21 Cycle 10 core leading. No changes in TVA's RBM TS operability requirements proposed in TS-353R1 and TS-353S1 i
resulted from the analysis.
Results of the RWE analysis will i
also be included in the Unit 2 Cycle 10 SRLR which is scheduled to be issued later this month.
For future core reloads, the NON l
issue will be addressed as part of the standard reload analysis
-in a like manner.
7 There re no commitments in this letter.
If you have further gutstions, please contact me at (205) 729-2636.
Sincerel
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0s T. E. Abney p Manager of 4censirg and Indus ry Aff its Enclosure cci see page 3 5
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U.S. Nuclear Regulatory Commission Page 3-l August 20, 1997 L
Enclosure cc (Enclosure):
Mr. Mark S. Lesser, Branch Chief i
U.S. Nuclear Regulatory Commission Region II Atlanta Federal Center 601 Forsyth St., Suite 23T85 1
Atlante, Georgia 30303 NRC Resident Inspector Browns Ferry Nuclear Plant 10833 Shaw Road Athens, Alabama 35611 Mr. Joseph F. Williams, Project Manager U.S. Nuclear Regulatory Commission i
One White Flint, North l
11555 Rockville Pike Rockville, Maryland 20852 i
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l ENCLOSUllE i
GE LE'ITElt - ItESULTS OF UNIT 2 CYCLE 10 ItWE ANA13 SIS l
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LB#: 262 97 112 Mr. T A Keys oc:
D. E. Porter Manager, BWR Fuel Engineering L F. Rubino Tennessee Valley Authority G. A.Watford 1101 Market Street, BR6A Chattanooga, TN 37402 2801
Subject:
Browne Ferry Unit 2 Cycle 10 Rod Withdrawal Error Results Summary
Dear Mr. Keys:
At the request of Mr. B. C. Morris at Browns Ferry, please find encioned a summary of the Browns Ferry 2 Cycle 10 Rod Withdrawal Error (RWE) results. This summary is a copy of the Section 10 from the Browns Ferry 2 Cycle 10 Supplemental Reload Lloonsing Report (J11 031448RLR), which has been provided to TVA in draft form. The RWE analysis is verthed; however, verification on the SRLR is pom$ing inclusion of the references to GE Nuclear Services' final reports.
Verfication of the RWE analysis is contained in DRF #J1103144. We will advise you of completion of verification of the SRLR with the issuance of the offlonel, final SRLR document.
If there are any questions, please do not hesitate to call me at (910) 675 5838.
Very truly yours -
B. R. Fixdwr Technical Program Manager Attachmert(1 page) i
s i
- 10. Local Rod Withdrawal Error (With Limiting Instrument Failure) ADO Summary Rod withdrawal error (RWE) is analyzed in General Electric BWR Licensing Report Mulmum Extended Load Line Limit and ARTS Improvement Program Analysesfor Browns Ferry Nuclear Plant Units 1, 2 and 3, NEDC 32433P, dated April 1995. His analysis has been extended by Power Uprate Evaluation Task Reportfor Brosms Ferry Units I, 2, and 3 Transient Analysis, GE.NE D13 01866 0$,
dated July 1997, which covers the gel 3 fuel type, in addition, a cycle specific n>d withdrawal crTor analysis was performed for Drowns Ferry.2 Cycle 10. This cycle specific analysis demonstrates that all fuel types in the Cycle 10 core are bounded by the generic RWE analysis results from NEDC.32433P and GE.NE.Bl3 01866 0$. For Cycle 10, an RDM setpoint of 114.0% tanalytical limit, based on no RDM filter) was chosen, and this yields a ACPR of 0.24, based on these generic analyses. The cycle.
specific analysis demonstrates that the 1% plastic strain requirement is satisfied, assuming no credit for the RDM system, in accordance with the ARTS /MELLLA Technical Specification operability requirements.
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