ML20247R959
| ML20247R959 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 07/31/1989 |
| From: | Hairston W GEORGIA POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 4321N, GL-88-16, HL-661, NUDOCS 8908080148 | |
| Download: ML20247R959 (20) | |
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HL-661
.l 4321N July 31, 1989
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U.S. Nuclear Regulatory Commission
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ATTN: Document Control Desk Washington, D.C.
20555.
PLANT HATCH - UNITS'1, 2 NRC DOCKETS 50-321, 50-366 OPERATING LICENSES DPR-57, NPF-5
'i REQUEST FOR ADDITIONAL INFORMATION:
REMOVAL OF CYCLE-SPECIFIC PARAMETER LIMITS Gentlemen:
On June 22, in80, Georgia Power Company (GPC) submitted a request to revise Technical Specifications (TS) for both units at Plant Hatch.
The proposed TS would remove certain fuel and core operating limits and place them in a Core Operating Limits Report (COLR), consistent with the NRC guidance provided in Generic Letter 88-16.
Subsequent to our submittal, GPC was informed that the NRC has agreed - to permit utilities to place Linear Heat Generation Rate (LHGR) limits in the COLR. Also, the NRC has requested GPC provide a druft COLR for their use in reviewing our June 22, 1989 submittal. provides a draft COLR for Plant Hatch Unit 2, Cycle 8 (current operating cycle).
A final COLR will be issued within 60 days following NRC approval of our proposed TS ame,ndment.
provides revised TS pages and page change instructions to delete LHGR limits from' the Technical Specifications.
The LHGR limits will be relocated to*the COLR.
The Basis..for Change Request and 10 CFR 50.92 evaluation' for the relocation of fuel thermal limits provided in our June 22,1989' submittal is applicable to this change.
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- Georgia Power A U.S. Nuclear Reg'ilatory Commission
]
July 31, 1989 Page Two Please contact this office if you have questions.
Sincerely, it)..h H. G. Hairston, III GKM/et
Enclosures:
1.
Draft COLR for Unit 2 Fuel Cycle 8 (Reload 7) 2.
Page Change Instructions c: Georgia Power Comoany Mr. H. C. Nix, General Manager - Nuclear Plant Mr. J. D. Heidt, Manager Engineering and Licensing - Hatch GO-WORMS U.S. Nuclear Reaulatorv _ Commission. Washington. D.C.
Mr. L. P. Crocker, Licensing Project Manager - Hatch E Nuclear Reaulatoiv Commission. Reaion 11 Mr. S. D. Ebneter, Rajional Administrator Mr. J. E. Menning, Senior Resident Inspector - Hatch l
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1 4321N n
1 ENCLOSURE 1 DRAFT
)
I GEORGIA POWER COMPANY I
EDWIN I. HATCH HUCLEAR PLANT UNIT 2 FUEL CYCLE 9 (RELOAD 7)
CORE OPERATING LIMITS REPORT REVISION O l
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SOUTHERN COMPANY SERVICES, INC.
P. O. BOX 1295 BIRMINGHAM, AL 35201 I
1.
ETR__0 DUCT 10N This Core Operating Limits Report for Hatch Unit 2 Cycle 8 is prepared in accordance with the requirements of Hatch Technical Specification 6.9.1.11.
The core operating limits presented-here were developed using NRC-approved methods (References 1 and 2).
Results from the reload analyses for. the General Electric fuel in Hatch Unit 2 Cycle 8 are documented in Reference 3.
The following cycle specific core operating limits are included in this report.
a.
Control Rod Program Controls - Rod Block Monitor (Technical Specification 3/4.1.4.3) b.
Average Planar Linear Heat Generation' Rate (APLHGR) Limit (Technical Specification 3/4.2.1) c.
Minimum Critical Power Ratio Operating Limit (Technical Specification 3/4.2.3) d.
Linear Heat Generation Rate (LilGR) Limit (Technical Specification 3/4.2.4) 2.
ROD BLOCK MONITOR (TECHNICAL SPECIFICATION 3/4.1.4.3)
Both Rod Block Monitor (RBM) channels shall be operable as specified in Technical Specification 3/4.1.4.3 and when:
a.
THERMAL POWER is < 90% of RATED THERMAL POWER and the MCPR is less than 1.70, or b.
THERMAL POWER is 1 90% of RATED THERMAL POWER and the MCPR is less than 1.40.
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3.
'APLHGR LIMIT (TECHNICAL SPECIFICATION 3/4.2.1)
The APLHGR limit is given by the applicable rated-power, rated-flow limit taken from Figures 3-3 through 3-5, multiplied by the smaller of either:
b.
The factor given by Figure 3-1, or b.
The factor given by Figure 3-2.
For the fuel types whose APLHGR limits are'shown in Figures 3-3 through 3-5, the APLHGR limit shown shall be applied to each axial location in the-fuel assembly.
4.
TWO RECIRCULATION LOOP 0PERATION The MCPR operating limit (OLMCPR) is a function of fuel design, average scram time, core flow, number of operating recirculation loops, and core power.
4.1 Two Recirculation loop Operation For 25% $ Power < 30%, the OLMCPR is given in Figure 4-1.
For Power 2 30*/.,
the OLMCPR is the greater of either:
a.
The applicable limit determined from Figure 4-2, or b.
The appropriate Kp giveri by Figure 4-1, multiplied by the-appropriate limit from figure 4-3, where ave T _, whichever is greater l
v-0 or _T B
TA-TB l
1.I
where:
TA = 1.096 sec (Specification 3.1.3.3, scram time limit to notch 36)
_1/2 TB - p + 1.65
__N}_
a n
INj
_ i-1_
0.822 sec (mean scram time used in the transient where:
p analysis)
.018 sec (standard deviation of p) a =
n INj Tj ave =
i"I T
n INj i=1 where:
n-number of surveillance tests performed to date in the cycle Nj - number of active control rods measured in the ith surveillance test average scram time to notch 36 of rods in Tj the ith surveillance test N1-total number of active rods measured in Specification 4.1.3.2.a Note that T - 1.0 prior to the initial scram time measurements for the cycle performed in accordance with Specification 4.1.3.2.a because Tave is assumed equal to TA (Specification 4.2.3.1.a).
3
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I 4.2 Sinale Recirculation Loon ODeration
~
i for single-loop operation, the' MCPR operating limit shall be 0.01 greater
.I than the two-loop value which is determined as specified in Section 4.1.
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5.
LHGR LIMIT (TECHNICAL SPECIFICATION 3/4.2.41 I
The LHGR limit shall be 13.4 kw/ft for all 8x8 fuel.
There is no corresponding limit for 9x9 fuel.
1 l
6.
REFERENCES 1.
" General Electric Standard Application for Reactor Fuel,"
NEDE-240ll-P-A-9 (September 1988).
2.
Letter, L. P. Crocker (NRC) to J. P. O'Reilly (GPC), " Issuance of Amendment Nos. 151 and 89 to Facility Operating Licenses DPR-57 and NPF Edwin I. Hatch Nuclear Plant Units 1 and 2 (TACS 66524/66525)," January 22, 1988.
3.
" Supplemental Reload Licensing Submittal for Edwin I. Hatch Nuclear Plant Unit 2, Reload 7, Cycle 8," GE Document 23A5884 (January 1988).
4.
"Edwin I. Hatch Nuclear Plant Units 1 and 2 SAFER /GESTR-LOCA Loss-of-Coolant Accident Analysis," NEDC-31376-P, December 1936, as amended.
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i ALL 8 X 8 AND 9 X 9 LFA FUEL TYPES I
FIGURE 3isiBiit )
i f-J C>' CLG 2 AiNRiys;YS R&.SQy I
nCID J
ENCLOSURE 2 PLANT HATCH - UNIT 1 NRC DOCKET 50-321 OPERATING LICENSE DPR-57 RE0 VEST TO REVISE TECHNICAL SPECIFICATIONS REACTIVITY CONTROL SYSTEMS AND REMOVAL OF CYCLE-SPECIFIC PARAMETER LIMITS PAGE CHANGE INSTRUCTIONS Removed Paae Insert Pace iii iii X
X xi 1.0-7 1.0-7 1.1-6 1.1-6 1.1-7 1.1-7 1.1-8 1.1-8 3.3-5 3.3-5 3.3-6 3.3-6 3.3-7 3.3-7 3.3-9 3.3-9 3.3-15 3.3-15 3.3-16 3.3-16 3.3-18 3.3-18 3.6-22 3.6-22 3.11-1 3.11-1 3.ll-la 3.11-la 5.11-2 3.11-2 3.11-2a 3.11-3 3.11-3 3.11-4 3.11-4 i
3.11-4a J
Figure 3.11-1, Sheets 1 through 8 Figure 3.11-3 Figure 3.11-4 1
Figure 3.11-6 1
6-15d 6-15d i
l Page 1 of 1
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4 LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REOUIRENENTS 3.11.B.
Linear Heat Generation Rate (LN6R) 4.11.B.
Linear Heat Generation Rate (LkGR)
During power operation, the LHGR The LH6R shall be checked daily i
shall not exceed the limiting, during reactor operation at > 255 l
vatee provided in tne Core Oper-rated thermal power.
~
sting Limits Report. If at any time during l
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j HATCH - UNIT 1 3.11-la Proposed 15/02624/006-157
ENCLOSURE 21 PLANT HATCH - UNIT 2 NRC DOCKET 50-366 OPERATING LICENSE NPF-5 RE0 VEST TO REVISE TECHNICAL SPECIFICATIONS REACTIVITY CONTROL SYSTEMS AND.
REMOVAL OF CYCLE-SPECIFIC PARAMETER LIMITS PAGE CHANGE INSTRUCTIONS Removed Paae Insert Pggg I
I XVI XVI.
1-2 1-2 B2-1 B2-1 B2-2 B2-2 B2-3 B2-3 B2-4 B2-4 B2-5 B2-5 B2-13 B2-13 3/4 1-4 3/4.'l-4 l
3/4 1-14 3/4 1-14 3/4 1-15 3/4 1-15 j
3/4 1-16 3/4 1-16 3/4 1-17 3/4 1-17 3/4 2-1 3/4 2-1 3/4 2-2 3/4 2-2 3/4 2-3 3/4 2-3 3/4 2-4 3/4 2-4 1
3/4 2-4a 3/4 2-4b 3/4 2-4c 3/4 2-4d 3/4 2-4e - 3/4 2-41 3/4 2-4j 3/4 2-4k 3/4 2-6
.3/4 2-6 3/4 2-7 3/4 2-7 3/4 2-7a 3/4 2-7a 3/4 2-7b 3/4 2-7b - 3/4.2-7d l
l 3/4 2-7c 3/4 2-7d l
3/4 2-8 3/4 2-8 1
3/4 3-39 3/4 3-39
)
3/4 3-42 3/4 3-42 l
3/4 10-2 3/4 10-2 i
B'3/4 1-3 B 3/4 1-3 B 3/4 2-1 B 3/4 2-l' B 3/4 2-2 B 3/4 2-2 4
Page 1 of 2.
O
' ENCLOSURE 2 PLANT HATCH - UNIT 2 NRC DOCKET 50-366 l
OPERATING LICENSE HPF-5 l
RE0 VEST TO REVISE TECHNICAL SPECIFICATIONS REACTIVITY CONTROL SYSTEMS AND REMOVAL-OF CYCLE-SPECIFIC PARAMETER LIMITS PAGE CHANGE._ INSTRUCTIONS Removed Pace Insert Paag B 3/4 2-3 B 3/4 2-3 B 3/4 2-4 8 3/4 2-4 8 3/4 2-6 B 3/4 2-6
-B 3/4 4-1 B 3/4 4-1 6-14d 6-14d-1 i
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Page 2 of 2-
. POWER DISTRIBUTION LIMITS i
3/4.2.4 LINEAR HEAT GENERATION RATE LIMITING CONDITION FOR OPERATION 3.2.4 ALL LINEAR HEAT GENERATION RATES (LHGRs) shall not exceed their applicable LHGR limits provided in the CORE OPERATING LIMITS REPORT.
APPLICABILITY: CONDITION 1, when THERMAL POWER 225% of RATED THERMAL POWER.
ACTION:
With the LMGR of any fuel rod exceeding its LHGR limit provided in the CORE OPERATING LIMITS REPORT, initiate corrective action within 15 minutes and continue corrective action so that the LHGR is within the limit within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or reduce THERMAL POWER to less toen 25% of RATED THERMAL POWER within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
SURVEILLANCE REQUIREMENTS 4.2.4 All LHGRs shall be determined to be equal to or less than their applicable LHGR limits provided in the CORE OPERATING LIMITS REPORT:
a.
At least orce per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, b.
When THERMAL POWER has been increased by at least 15% of RATED THERMAL POWER and steady state operating conditions have been established, and c.
Initially and at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> when the reactor is operating on a LIMITING CONTROL ROD PATTERN FOR LHGR.
l HATCH - UNIT 2 3/4 2-8 Proposed TS/0273q/006-66
___