ML20247R162
| ML20247R162 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 03/31/1989 |
| From: | Kemper J PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| RTR-REGGD-01.099, RTR-REGGD-1.099 NUDOCS 8904070260 | |
| Download: ML20247R162 (25) | |
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PHILADELPHIA ELECTRIC COMPANY 2301 MARKET STREET P.O. BOX 8699 PHILADELPHIA A PA,19101 (215)841 4500 JOHN S. KEMPCR EENIOR VIC E. PRESIDE NT
- NUCLE A R March 31, 1989 U. S. Nuclear Regulatory Conmission Docket No. 50-353 Attn:. Document Control Desk Washington, DC 20555
SUBJECT:
Limerick Generating Station, Unit 2 Response to' Generic Letter 88-11
REFERENCE:
Letter from J. W. Gallagher (PEco) to T. E. Murley (NRC) dated Noventer 23, 1988 (Docket Nos. 50-277/50-278, 50-352/50-353)
Gentlemen:
In'the referenced letter, Philadelphia Electric Company (PECo) provided its response to the subject Generic Letter indicating that a fracture
. toughness analysis for Limerick Generating Station, Unit 2 (LGS-2) would be provided at a later date, and that a Technical Specification revision would be submitted, if necessary.
Attached is the fracture toughness analysis empleted for LGS-2 using the methods approved in Revision 2 of Regulatory Guide 1.99.
Since the LGS-2. Operating License has not yet been issued, PEco will continue to work with the Nuclear Regulatory Conmission Staff to develop appropriate Technical Specifications to reflect the results of this analysts.
PECo will also amend the Final Safety Analysis Report following the approval of this analysis.
If there are any questions please let me know.
Sincerely,
$ $;/=L f Attachments
- f HDH/dk/03228900 Copy to:
T. J. Kenny, LGS Senior Resident Inspector i
W. T. Russell, Region 1 Administrator I
R. J. Clark, LGS Project Manager f(
malBsti! SUMB a
n bec:
C. A. McNeill, Jr.
S26-1 S. J. Kowalski S25-1 E. J. Bradley S23-1 E. P. Fogarty S7-1 J. M. Madara, Jr.
57-1 G. A. Hunger, Jr.
S7-1 D. P. Helker S7-1 R. M. Krich S7-1 D. B. Fetters N4-1 L. B. Pyrih N2-1 T. E. Shannon-N2-1 A. J. Marie N2-1 H. D. Honan N2-1 G. M. Leitch LGS MC 200 P. J. Duca, Jr.
LGS MC AS-1 C. R. Endriss LGS MC A2-1 A. S. MacAinsh LGS MC 5B3-4 i
M. S. Iyer BPC/SF DAC NG-8 i
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a SASR 89-05 DRF 137-0010 IMPACT OF REGUIATORY GUIDE 1.99, REVISION 2 ON LIMERICK GENERATING STATION UNIT 2 BACKGROUND The pressure-temperature (P-T) curves in the Technical Specifications are established to the requirements of 10CFR50, Appendix G ll) to assure that brittle fracture of the reactor vessel is prevented.
Part of the analysis involved in developing the P-T curves is to account for neutron irradiation embrittlement effects in the core region, or beltline.
In the past, Regulatory Guide 1.99, Revision 1 [2] has been used to predict the shift in nil-ductility reference temperature (RTNDT) as a function of neutron fluence in the beltline region.
Regulatory Guide 1.99, Revision 1 (Rev 1) was developed assuming that copper (Cu) and phosphorus (P) were the ' key chemical elements influencing embrittlement.
Regulatory Guide 1.99, Revision 2 [3] (Rev 2) was issued in May 1988.
Rev 2 represents the results of statistical evaluation of commercial' reactor surveillance test data accumulated through about 1984.
There are two basic factors used in the calculations to predict the shift in RTNDT shown in the regulstory guide, a chemistry factor and a fluence factor.
Both of these factors remained the same from Rev 1 to Rev 2 of the regulatory guide.
However, the method used to calculate each factor has been significantly changed.
The chemistry factor (CF) has been changed from an equation based on Cu and P in Rev 1 to tables of CF values based on Cu and nickel (Ni), with separate tables for plates and for welds.
The fluence fector has been modified in Rev 2 to a somewhat more complex form.
Generic Letter 88-11 [4] requests an evaluation of the impact of Rev 2 on existing P-T curves, and a schedule to implement Rev 2.
Based on that request, the Rev 2 impact evaluation for Limerick Unit 2 and the corresponding results are presented here.
Actions required for implementation of Rev 2 are also presented.
)
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4 IMPACT EVALUATION The beltline region in the Limerick 2 plant consists of three shell course No. 1 plates, three shell course No. 2 plates, and their associated welds.
Two categories of-beltline welds are identified:
" shop" welds and " field" welds.
The shop welds represent vertical seams which were made prior to shipment of pre-assembled ring segments to the Limerick 2 plant site.
The field welds (i.e.,
girth welds) were. made at the plant site.
Since some weld metal heats are not 1
traceable to specific welds, all weld metal heats were considered in this analysis. However, only a few of the most limiting weld heats of each category are documented.
The LPCI nozzles, because of their 17 2
exposure to a peak End of-Life (EOL) fluence (1.6 x 10 n/cm at the 17 1/4 thickness depth) in excess of 1 x 10 n/cm2 (E > 1MeV), are also considered.
Attachment A shows the details of the impact evaluation for Limerick Unit 2.
The process followed for each beltline material is described below.
Chemistry The chemistry data for all beltline region plates, beltline weld filler materials, and LPCI nozzles and welds shown in Attachment A were taken from the GE design record file material that supports Section 5.3 of the Limsrick 2 FSAR [5).
Initial RTET The values of initial RTNDT shown in the attachment were taken from the CE design record file material that supports Section 5.3 of the Limerick 2 FSAR [5).
These values were based on 30 f t-lb impact energy verification testing, with longitudinal Charpy specimens used for plate, done at the time of vessel fabrication.
The calculations of these initial RT values in the FSAR were based on a CE procedure NDT which established conservative values of RT from the fabrication NDT test data.
Since the initial RTNDT values are conservative, the term in the Rev 2 margin expression og is assumed to be zero.
l l
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Fluence The value of neutron fluence for. 32 effective full power years (EFPY) shown in Attachment A is based on peak fluence predictions as
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noted in the FSAR. Lead factors applicable to the use of this fluence value give a peak fluence value at the vessel inside surface, f surf-The Rev 1 calculations of RTNDT shift are based on a calculated value of fluence 1/4 thickness into the vessel wall from the inside surface (1/4 T).
The Rev 2 method is to take the calculated fluence at the vessel inside surface, fsurf, and attenuate that value to the depth x according to the relationship:
~
fx"fsurf (*
}-
ad
.i This method results in a slightly higher fluence at the 1/4 T location.
Surveillance Test Correction Factor i
Rev 1 allows for consideration of credible surveillance data when it becomes available.
If the RTNDT shift seen in the surveillance data is larger than initial predictions, Rev 1 shift predictions are increased by this factor.
For Limerick Unit 2, where surveillance testing has not yet b'sen performed, the correction factor does not apply, and is set to 1.0.
SHIFT and Adiusted Reference Temperature (ART)
The RT shift calculations in Attachment A are based on the NDT procedures in Rev 1 and Rev 2.
For Rev 1, the value of SHIFT is computed with the equation:
SHIFT - (STF)*[40 + 1000(%Cu -.08) + 5000(%P -.008))*(f)0.5 where STF - surveillance test correction factor 19 f - fluence for the given EFPY / 10 3
4 For Rev 2, the value of SHIFT consists of two terms:
SHIFT - ARTET + Margin l
ET - [CFJ*f(0.28 '- 0.10 log f) where ART Margin - 2(ay.+ a 2).5, 2
3 l
Chemi,try factors (CF) are tabulated for welds and plates in Rev 2 of l
the regulatory guide.
The margin term a3 has set values in Rev 2 of 17'F for plate and 28'F for weld.
However, og need not be greater than 0.5* ARTET
- The values.of ART in the attachments are computed by adding the SHIFT terms to the values of initial RTET ART - initial RTNDT + SHIFT.
LPCI Nozzles A review of all LPCI nozzles in the beltline region shows that a conservative estimate of Cu.15% and the measured Ni-0.82% applies for the worst case LPCI nozzle.
Based on these chemistry values, the worst case LPCI nozzle has a Rev 2 ART of 32.1*F at 32 EFPY.
Since this is less than the 40*F RT applied to the limiting vessel NDT discontinuity curves, the LPCI nozzle is bounded by the limiting vessel discontinuity curves.
Further, the most limiting LPCI weld, 432A2671 / Iot H019A27A, has a Rev 2 ART of 4.9'F at 32 EFPY.
Based on these two points, further consideration of the LPCI nozzles in this evaluation is unnecessary.
1
O RESULTS AND RECOMMENDATIONS Results and Conclusions The impact of implementing Regulatory Guide 1.99, Revision 2 (Rev 2) can best be determined by comparing the Adjusted Reference Temperature (ART) values based on Regulatory Guide 1.99, Revision 1 (Rev 1) and Rev 2.
Table 1 shows the ART values at 12 effective full power years (EFPY) and at 32 EFPY for each beltline material in Limerick Unit 2.
The following conclusions are drawn from the results in this table:
~
1.
The Rev 2 ART values at 32 EFPY for this unit are below 200'F, which is the allowable limit in 10CFR50, Appendix G.
Therefore, implementation of Rev 2 will not result in any additional analysis, testing or provisions for thermal annealing.
2.
The Rev 1 ART value which applies to the beltline P-T curves (A',
B', and C') in the Technical Specifications is 75'F at 32 EFPY.
The maximum Rev 2 ART value in Table 1 is 119.5'F at 32 EFPY.
Therefore, these Rev 1 32 EFPY P-T curves are less conservative than 32 EFFY curves that would be generated with Rev 2.
These Rev 1 32 EFPY beltline curves, based on an ART of 75'F, are applicable to 5.5 EFPY if ART is calculated according to Rev 2 methods.
The non-beltline curves (A, B, and C), applicable per Rev 1 to 12 EFPY, have a corresponding ART of 61.3*F.
These non-beltline curves are applicable to only 2.5 EFPY when ART is calculated according to Rev 2 methods.
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a Recommendations Based on the results on the previous page, the following recommendations are made concerning Rev 2 implementation:
The implementation of Rev 2 results in calculated. 32 EFPY ART values more conservative than those of Rev 1 at 32 EFPY.
Therefore, revision to the P-T curves is appropriate.
Philadelphia Electric has authorized the revision of the P-T curves according to the methods of Rev 2.
When Rev 2 is implemented, the P-T curves will be changed to include the Rev 2 shift corresponding to an appropriate value of EFPY.
Changes will be required.to section 5.3 of the FSAR, as well as section ".
3/4.4.6 and the corresponding bases of the Technical Specification.
I l
Table 1 COMPARISON OF REV 1 AND REV 2 ART VALUES FOR LIMERICK UNIT 2 12 EFPY 32 EFPY Rev 1 Rev 2 Rev 1 Rev 2 Beltline Comeonent M (*F)
ART (*F)
ART (*F)
ART (*F)
Unit 2 Plates:
53312-1 29.3 59.3 41.5 84.6 33416 1 61.3 95.3 74.8 119.5 C9621-2 44.3 82.0 58.5 105.4 C9569-2 25.2 49.9 34.9 75.7 C9526-1 28.3 50.2 39.8 76.2 C9526 2 28.3 50.2 39.8 76.2 Unit 2 Shop Welds:
432A2671 7.3 17.5 19.5 36.5 661A746 1.3 2.4 14.8 16.9 Unit 2 Field Welds:
07L857 6.2 16.4 13.9 30.9 09M057
-26.9
-13.6
-21.1 0.9 03M014
-21.8
-23.1
-14.1
-16,0 640892
-42.7 6.6
-31.8 49.7 LPCI Nozzle and Weld:
l-Nozzle (ID# 98-1-3) 12.4 32.1 Weld (Heat 432A2671) 0.0 4.9 IL_-_________---___.
o..
e REFERENCES
[1]
" Fracture Toughness Requirements," Appendix G to Part 50 of Title 10 of the Code of Federal Regulations, July 1983.
{2)'
- Effects of Tasidual Elements on Predicted Radiation Damage to Reactor Vessel Materials,"
USNRC Regulatory Guide 1.99, Revision 1 April 1977.
[3]
" Radiation Embrittlement of Reactor Vessel Materials," USNRC Regulatory Guide 1.99, Revision 2, May 1988.
[4]
"NRC Position on Radiation Embrittlement of Reactor Vessel Material and Its Impact of Plant Operations," USNRC Generic,,
Letter 88-11, July 1988.
~~
[5] Limerick Unit 2 - FSAR I
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1 ATTACHMENT A COMPARISON OF IRRADIATION EMBRITTL2 MENT PREDICTIONS OF REGUIATORY GUIDE 1.99, REVISIONS 1 AND 2 FOR LIMERICK UNIT 2 l-Se l
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