ML17216A408
| ML17216A408 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 01/15/1986 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17216A407 | List: |
| References | |
| NUDOCS 8601230545 | |
| Download: ML17216A408 (9) | |
Text
~~+ Rf0I
+
0 ty n0 I
gO
+a*++
t UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON; O. C. 20555 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 71 TO FACILITY OPERATING LICENSE NO.
DPR-67 FLORIDA POWER 5 LIGHT COMPANY ST.
LUCIE PLANT, UNIT NO.
1 DOCKET NO. 50-335 INTRODUCTION Florida Power 5 Light Company (FP8L), by letter from J.
W. Williams, Jr.
(FP&L) to H. L. Thompson (NRC) dated July 19, 1985, has requested two revisions to St. Lucie Plant, Unit No. I.Technical Specification 3/4.1.3, "Movable Control Assemblies."
The first revision would permit full power operation for a specified period of time following an inadvertent single dropped control element assembly (CEA).
This specified amount of time depends on the initial pre-drop value of the integrated radial peaking factor (F ), which is measured at the plaht during normal power distribution surveilla(ces.
The present Technical Specifications require a prompt and significant reduction in thermal power prior to attempting realignment of the dropped CEA.
The second revision is merely a reformulation of existing Action Statement C into two separate action statements, C and H, to more clearly associate any required operator action with the applicable analysis assumptions requiring that action.
SAFETY EVALUATION In order to allow continued full power operation for a specified period of time in the event of a single dropped CEA, the licensee performed analyses to determine the increase in assembly peak FR values following a dropped CEA event.
The CEA drop initially causes a decrease in reactor power with a resulting decrease in average reactor coolant temperature.
The reactor protection system inhibits automatic CEA withdrawal during the event.
- However, because of the negative value of the moderator temperature coefficient at end of cycle, this temperature decrease may cause the reactor power level to return to its initial power level.
The presence of the dropped CEA would then result in a distorted core. power distribution and increased power peaking factors.
g BbDi230545 860i0~335 pDR ADOCK, 05000335 p
J h
For St. Lucie l, margin was designed into the departure from nucleate boiling (DNB) limiting condition of operation (LCO) by selecting a
10% greater input value (1.87) of F," including uncertainties, than the maximum al;lowed Technical Specification limit of 1.70.
Even using the input value of 1.87 in the thermal margin analysis, the resulting DNBR values were greater than the DNB specified acceptable fuel design limits (SAFDL).
Therefore, the margin between the permissible normal operation limit of 1.70 and the 1.87 thermal margin input value can be utilized as available overpower margin for the single CEA drop analysis.
The results of the dropped CEA analyses show that the increase in assembly peak F
values following' dropped CEA event is a function of the reactivity worth Imf the dropped CEA and the assembly's distance from the dropped, CEA.
Because of this, an assembly other than the one with the initial core maximum F
can have a larger percent increase than the core maximum F
assembly.
The licensee has shown that the maximum F
increase anywhere in tie core imaediately following a CEA drop would be less th)n 10K for cycles 5 or 6, thereby meeting the available overpower margin.
One hour following a CEA drop, the maximum increase in FR anywhere in the core could be as high as 11.7%.
This means that an initial FR of no greater than 1.67 would be required in order to meet the 1.87 thermal margin input value mentioned above.
The licensee has proposed to incorporate the attached Figure 3.l-la into the St. Lucie l Technical Specifications showing the allowable time to realign a
dropped CEA as a function of the initial value of F The figure permits only 15 minutes of full power operation when the pre-drof value of F
equals 1.70 even though the analyses show that at least l hour would be permissible.
As the pre-drop value of F decreases to 1.67, operation at full power for up to l hour is allowed.
Based on the CEA drop analyses mentioned previously, the staff finds this acceptable.
The second proposed change reformulates the present action statement in Technical Specification 3/4. 1.3 into two separate action statements; one with applicability when CEAs are above the long term insertion limit (LTIL) and a
separate one when CEAs are inser ted beyond the LTIL.
Since this reformulation will aid the reactor operators to better understand the underlying technical basis of each specification and action statement and will also tend to standardize the specifications between St. Lucie l and 2, the staff finds it acceptable.
ENVIRONMENTAL CONSIDERATION This amendment involves a change in the installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20.
The staff has determined that the amendment involves no significant increase in the
- amounts, and no significant change in the types, of any effluentq 5hat may be released offsite, and that there is no significant increase fn ihfividual or cumulative occupational radiation exposure.
The Commission has previously published a proposed finding that the amendment involves no significant hazards consideration and there has been no public comment on such finding.
Accordingly,
the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 551.22(c)(9).
Pursuant to 10 CFR 551.22(b),
no environmental impact statement or environmental assessment need be prepared in connect%)n with the issuance of the amendment.
CONCLUSION We have concluded, based on the considerations discussed above, that (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed
- manner, and (2) such activities will be conducted in compliance with the Commission's regulations, and the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
Date:
January 15, 1986 Principal Contributors:
L. Kopp D. Sells
rr
Decdisber 1R'ci'o86"-
'ocket No. 50-335 Mr. J.
W. Williams, Jr.
Vice President Nuclear Energy Department Florida Power 5 Light Company P. 0.
Box 14000 Juno Beach, Florida 33408
Dear Mr. Williams:
DISTRIBUTION:
NRC PDR L PDR PBD¹8 Rdg FMiraglia PMKreutzer-3 DSells JPartlow LJHarmon SECY LFMB LTremper OPA ACRS-j.0 WRegan WJones TBarnhart-4 EJordan OELD PS Fi 1 es
+4 The Commission has issued the enclosed Amendment No. 70 to Facility Operating License No.
DPR-67 for the St. Lucie Plant, Unit No. l.
This amendment consists of changes to the Technical Specifications in response to your application dated October 17, 1985 as supplemented by letter dated December 2, 1985.
This amendment revises the Technical Specifications to change the Linear Heat Generation Rate (LHGR) Limiting Condition for Operation (LCO) from a constant value of 15.0 Kw/ft to an axially dependent limit.
In addition, the Local Power Density LCO curve and the associated Bases are changed.
The fuel densification and thermal expansion uncertainty factor of 1.01 is deleted.
Added is a license condition requiring the submittal of a supplement to EXXON Report XN-NF-85-117 for the Commission staff's review and approval.
This supplement is to cover the complete large break LOCA spectrum results to demonstrate full compliance with the cr iteria of 10 CFR 50.46 and Appendix K
to 10 CFR Part 50 with 15% tube plugging which will be considered following receipt of the supplement.
Action on your request to allow you to exceed the limits of Figure 3.2-1 during the performance of Specification 4. l. 1.4.2 is deferred until further justification is provided that shows that you can verify that the limit of 10 CFR 50.46 is not exceeded.
A copy of the related Safety Evaluation is also enclosed.
The notice of issuance wi'll be inciuded in the Cosmission's next bi-week1y Federal
~Re ister notice.
Enclosures:
l.
Amendment No.
70 to DPR-67 2.
Safety Evaluation cc w/enclosures:
See next page Sincerely,
/S/
Donald E. Sells, Project Manager PWR Project Directorate ¹8 Division of PWR Licensing-B PBD¹8*
PKreutzer 12/9/85 ql QL.oi g$q~ ~
See previous white for concurrences
¹8 PBD¹8*
OELD*
DSells;yf AThadani JMcGurren I >//~/8 12/9/85 12/10/85
4 H
A Er I a-h I
4
~
HI I u,l
.HI F
~
54 I'4 4
~ f 1
1E 1 E'H 4
I FH r
E Iu I,
I I
lr
'rl Hr h g
/HI 4
4 1
4 I I
I I
~
~
4 FH" I
H
Docket No. 50-335 Mr. J.
W. Williams, Jr.
Vice President Nuclear Energy Department Florida Power 8 Light Company P. 0.
Box 14000 Juno Beach, Florida 33408
Dear Mr. Williams:
DISTRIBUTION:
oc et
)
e NRC PDR L PDR PBD¹8 Rdg FMiraglia PMKreutzer-3 DSells JPartlow LJHarmon SECY LFMB LTremper OPA ACRS-10 WRegan WJones TBarnhart-4 EJordan OELD PS Files
+4 The Commission has issued the enclosed Amendment No.
to Facility, Operating License No.
DPR-67 for the St. Lucie Plant, Unit No. 1.
This amendment consists of changes to the Technical Specifications in re~gyge to your application dated October 17, 1985 as supplemented by letter dated December 2, 1985.
This amendment revises the Technical Specifications to change the L'inear Heat Generation Rate (LHGR) Limiting Condition for Operation (LCO) from a constant value of 15.0 Kw/ft to an axially dependent limit.
In addition, the Local Power Density LCO curve and the associated Bases are changed.
The fuel
...densification and thermal expansion uncertainty factor of 1.01 is deleted.
Added is a license condition requiring the submittal of a supplement to EXXON Report XN-NF-85-117 for the Commission staff's review and approval.
This supplement is to cover the complete large break LOCA spectrum results to
,demonstrate'full compliance with the criteria of 10 CFR 50.46 and Appendix K
to 10 CFR Part 50.
A copy of the related Safety Evaluation is also enclosed.
The notice of issuance will be included in the Commission's next bi-weekly Federal
~Re ister notice.
x I
~
Sincerely,
Enclosures:
l.
Amendment No.
to DPR-67 2.
Safety Evaluation cc w/enclosures:
Donald E. Sells, Project Manager PWR Project Directorate ¹8 Division of PWR Licensing-B See next page PBD¹8 PB 8
,PKiQfzer DSel 1 s;ef
".,>)~~f85
. 1~/85 P D¹8 AThadani pyq (85 OELD pb""
i y/~0/85
~
~
W n
, '\\
P I
T
~
f 1
f A
Fir. J.
W. Williams, Jr.
Florida Power
& Light Company St. Lucie Plant CC:
ter.
Jack Shreve Office of the Public Counsel Room 4, Holland Building Tallahassee, Florida 32304 Resident Inspector c/o U.S.
NRC 7585 S.
Hwy AIA Jensen
- Beach, Florida 33457 State Planning 8 Development Clearinghouse Office of Planning 8 Budget Executive Office of the Governor
'he Capitol Building Tallahassee, Florida 32301 Harold F. Reis, Esq.
Newman 8 Holtzinger 1615 L Street, N.W.
Washington, DC 20036 Norman A. Coll, Esq.
t',cCarthy, Steel, Hector and Davis 14th Floor, First National Bank Building tliami, Florida 33131 Administrator Department of Environmental Pegulation Power Plant Siting Section State of Florida 2600 Blair Stone Road Tallahassee, Florida 32301 Hr. Weldon B. Lewis, County Administrator St. Lucie County 2300 Virginia Avenue, Room 104 Fort Pierce, Florida 33450 Hr. Charles B. Brinkman, Manager Washington - Nuclear Operations Combustion Engineering, Inc.
7910 Woodmont Avenue
- Bethesda, Maryland 20814 f'r. Allan Schubert, Hanager Public Health Physicist Department of Health and Rehabilitative Services 1323 Winewood Blvd.
Tallahassee, Florida 32301 Regional Administrator, Region II U.S. Nuclear Regulatory Comission Executive Director for Operations 101 Yiarietta Street N.W., Suite 2900 Atlanta, Georgia 30323