Text

Letter Submitting Three Signed Originals and Forty Conformed Copies of Request to Amend Facility Operating License DPR-31 and DPR-41
	ML18227C824
Person / Time
Site:	Turkey Point
Issue date:	09/19/1974
From:	Robert E. Uhrig; Florida Power & Light Co
To:	Case E; US Atomic Energy Commission (AEC)
References
	Download: ML18227C824 (49)
	v • d • e

AEC DISTRIBUTION FOR PART 50 DOCKET MATERIAL (TEMPORARY FORM)

CONTROL NO:

FILE FROM: Florida Power 6 Light C Miami, Florida 33101

~ DATE OF DOC DATE REC'D LTR TWX RPT OTHER TO:

Mr. Case ORIG 2 si ed CC OTHER SENT. AEC PDR SENT LOCALPDR CLASS UNCLASS PROPINFO INPUT XXXX 48 50-2 0

NO CYS REC'D

-BOC.

T NO:

DESCRIPTION:

Ltr notarized 9-19-74, re their 6-21-74 ltr..

submitting proposed Amdt to Facility Oper Lic, consisting of revised Tech Specs regard Coolant Activity 6 Surveillance Requirements.

ENCLOSURES:

PL'ANT NAME:

Turkey Point Units 3 6 4 FOR ACTION/INFORMATION BUTLER (L)

W/ Copies CLARK (L)

W/ Copies PARR (L)

W/ Copies KNI EL (L)

W/ Copies SCHWENCER (L)

W/ Copies STOLZ (L)

W/ Copies VASSALLO (L)

W/ Copies PURPLE (L)

W/ Copies ZIEMANN(L)

REGAN (E)

W/ Copies W/ Copies DICKER (E)

~LEAR (L)

W/ Copies W/9Copies KNIGHTON (E)

W/ Copies W/ Copies YOUNGBLOOD (E)

W/ Copies W/ Copies INTERNALDISTRIBUTION G FIL

~AEC rOGC, ROOM P-506A

~UNTZI NG/STA F F CASE GlAMBUSSO BOYD MOORE (L) (BWR)

DEYOUNG (L) (PWR)

SKOVHOLT (L)

~ GOLLER (L)

P. COLLINS DENISE EG OPR I LE 5 R EG ION (3)

MOR R IS STEELE TECH REVIEW SCHROEDER MACCARY KNIG HT PAWLICKI SHAO STEI LO HOUSTON NOVAK ROSS IPPOLITO TEDESCO LONG LAINAS BEMAROYA VOLIMER DENTON G R IMES GAMMILL KASTNER BALLARD SPANGLER ENVIRO MULLER DICKER KNIGHTON YOUNG8 LOOD REGAN PROJECT LDR Cleveland HAR LESS LIC ASST DIGGS (L)

GEAR IN (L)

GOULBOURNE(L)

KREUTZER (E)

LEE (L)

MAIGRET (L)

REED (E)

SERVICE (L)

SHEPPARD (L)

SLATER (E)"

SMITH (L)

~EETS (L)

WI LLIAMS (E)

WI LSON (L)

A/T IND BRAITMAN SALTZMAN B. HURT PLANS MCDONALD CHAPMAN

~ DU BE w/input

~. COU~E D. THOMPSON (2)

KLECKER E ISENHUT EXTERNALDISTRIBUTION I OCAL PDR Homestead, FL.

~1 TIC (ABERNATHY)

(1)(2)(10) NATIONALLABS

'1 NSIC (BUCHANAN) 1.ASLBP(E/W Bldg, Rm 529) 1 ASLB 1

W. PENNINGTON, Rm E-201 GT 1 Newton Anderson 1

BSM SWINEBROAD, Rm E-201 GT 16 ACRSSQLcQIM6 SENT TO 1

CONSULTANTS Lic Asst.S, TEETS NEWMARK/8LUME/AGBA BI AN 1 PD R-SAN/LA/NY 1 BROOKHAVEN NAT LAB 1 G. ULRIKSON, ORNL 1 AGMED (RUTH GUSSMAN)

Rm 8-127 GT 1 R. D. MUELLER, Rm E-201 GT

4

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>" ~)I'<" (4 Nr. Bdaoa C. Case, Acting Director.'~~'-

>i,l Ir,:,'y, Directorate of Licensing

. Office of Repslation U. S. Atomic Energy Commission Qashington, D. C.

20545 gygll/y

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l FLORIDA POWER 5 LIGHT COMPANY Soptombor 19, 1974 Dear 1h. Ceset Ro!

Tuxkey Point Plant, Units 3 end 4 Docket,Nos, 50<<250 50-251, Proposed Amen nt Co Pacility'retin

'Licenses MR-31 aad DPR-41 Xn accordance with 10 CFR 50,30> Plorida Power 6 Light Company submits herewith throe signed originals and forty"(40) conformed copios of e propoood amendment to Facility Operating Licenses"DPR-31 and DPR-41.

This submittal replaces oux'orresponding Juno 21, 1974,- requost to amend tho Paeility Operating Licenses.

The changes are aa 'set forth in, Cho attached re-vised Technical Specification pages (Appendix A to DPR-31'and DPR-41) end are as described below!

Pa 6 3s1~5 Xn subsection 3.1.4 (in the first sentence) yCi/ce hes been changed to "micro-euries pex milliliter". This change was made to show tho actual moeoured unit, milliliter(liquid measurement) as opposed to cubic centimotor (gaseous measure-mone)

~

A sentence was also added to the ond of Cho first pereoroph in subsoction 3.1.4.

This eliminates tho monthly testing of the dogeoed reactor coolant activity unless the total activity, excluding tritium, is sufficiently high as to warrant a monthly Cast'.

The monthly test, results of the degesed reactor coolant ectivity Gxo normally so low that they provide data which is of little use.

Realistically, monthly Costing is not, necessary unless tho ectivity approaches tho level of 135/H,

ised, 30 mCi/m1.o Since Che specific activity predominately comes from the noble gesosy we propose to Cest the noble gas activity monthly (ooe the proposed change to Table 4.1-2),

Mth the gross reactor'oolant activity determined daily and the noble gas activity determined monthly, this xeducos further che need to determine Cho total specific activity of the degased xeaetor coolant on a monthly besiso

,HEI.P'ING BUILD FLORIOA

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Table 4.1-2 In item (1), the frequency of the radiochemistry analysis gas changed fxom monthly to semi-annually and the name ~ras changed to Isotopic Determination.

The isotopic determination and E determination vore grouped Cogethex'nd a

requirement added to increase the frequency of the E determination and the isotopic determination to monthly if the total reactor coolant activity, ez-clucfing tritium, ezceeded 30 yCi/N1 (see the proposed change to subooction 3+1.4, page 3.1-5).

78th the E and isotopic determination required aemi-annuollyf the mazimum time between CGQCB %fas changed to 240 days to bo consis-tent Wth the new fxequency definitions (aee the proposed chango.

Co Section 4.0, Pago 4.1-1),

A requirement was also added to perform a noble gas isotopic determination

monthly, Since tho activity of the reactoX'oolant io predominately'ue Co Che noble gases, a monthly isotopic determination viU. provide more useful data on reactor coolant activity A requirement to tept for fluoridis ia, the roactor coolant Oystem cmo also incorporated into tho table.
Subsection 3.1.5 specifies maximum fluox'ido, chloride and ozygen concentrations.
To properly limit the concentration requires testing the reactor coolant system for Chess elements.
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He. Edson C. Case, Acting Director Page Three September 19, 1974 fluoride has not beer included in tho table, it has been included in the testing.
This change provides the necessary consistency between Table 4.1-2 and subsection 3,1i5i In Xtem (S), the frequency of the rod dx'op time toots have been changed to require that the tests be performod only after maintenance has been per-formed on the control rods.
Xt is not the intent of this specification to requixe the control rods to be tested following any maintenance but only maintenance involving the contxol rods.
Xn Item (9), the frequency of the refueling system interlocks check has been modified to clarify when the equipment check is to take place.
Punctionally checking the equipment px'ior to each refueling shutdown is not practical due to accessibility limitations in containment during operation.
Xt is moro appropriate to check the equipment at each refueling shutdown prior to handling the fuel.
By reducing the time between the equipment check and the actual fuel handling operation> potential operational difficulties will be minimised.
'n Xtem (10), the testing requirement. has been eliminated when the accumulator is drained.
Xt is necessary to drain an accumulatox in order'o work on certain safety in)ectioa, system components.
The length of time the accumulator may be x'equired to be drained could conceivably interfere with the testing require-ment.
This change wQ1 prevent a conflict of this nature from occurx'ing.
Xn Item (14), the testing requirement has also been eliminated when the stcam genex'ator(s) is (are) drained.
Like the accumulator, it may be necessary to drain the steam generator(s) for repair or inspection.
The length of time the steam generator(s) may bo required to be drained could conceivably inter-fere with the testing requirement.
This change willprevent conflicts of this nature from occurring.
In Item (17), the maxhxum time between tests of the turbine stop and control valvesy xeheatex'top and intercept valves has been added to more clearly define the testing frequency.
A provision was also made to exempt the teat from being required during shutdown.
The purpose of the test is to demonstrate that tho valves will function as required under oporating conditions.
Testing the valves while the reactor is shutdown would give no indication of their capability to function properly during reactor opexation.
Table 4o12 Sheet 4
The frequency definitions were deleted because they are now stated at the beginning of Chapter 4 (see the proposed change to Section 4.0, Page 4.1-1).
Pa e B3.1-6 The bases have been made consistent with the proposed Technical Specifications.
M. Edson C. Case, Acting Dixector Page Pour September 19, 1974 Pa e B3.1-8 Addition
\\
No,change has been made to the text.
The proposed change to Page B3.1-6 resulted in the addition of a new page.
Ve have reviewed these changes and have concluded that they do not involve any significant hazards considerations and thexe is reasonable assurance that the health and safety of the public vQ.1 not be endangered.
Very truly yours, Robex't E. Uhrig Vice President
(
REU/DWR/cpc Attachment cc!
Nr. Jack R. Naenan
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Effort 8. Uhrig, being first duly sworn> deposes and says'hat he ia a Vice President of Plorida Power s Xight Company~
the Xicensee hereini That, ho has executed the foregoing instruments that the statements made in this said instnunent are true and correct to the best of his knowledge, information and beliefs and that'he is authorized to execute the instmnont of said Iicensee.
Robert E, Uhrig Subscribed to and sworn.to before ne tMs day 0 p 1974, cxDS c4~8 Mater public in and for the ounty of Dado> State of Florida p
"O @A'~"'P<<RIOAat I,ALOE AOTAPY PIIII1I
.1'It', OOMMIMIOiY EXPIRES APR
'PRIL 2, 197t'i u mytuuis noNwso Aa"%~4
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P.O, 8OX 3100 IIIIIAMI,FLORIDA 33I01 pig FLORIDA POWER 5 LIGHT COMPANY September 19, 1974 Mr. Edson G. Case, Acting Director Directorate of Licensing Office of Regulation U. S. Atomic Energy Commission Washington, D.
C.
20545
Dear Mr. Case:
Re:
Turkey Point Plant Units 3 and 4
Docket Nos. 50-250 and 50-251 Proposed Amendment to Facility 0 eratin Licenses DPR-31 and DPR-41 In accordance with 10 CFR 50.30, Florida Power 6 Light Company submits herewith three signed originals and forty (40) conformed copies of a proposed amendment to Facility Operating Licenses DPR-31 and DPR-41.
This submittal replaces our corresponding June 21, 1974, request to amend the Facility Operating Licenses.
The changes are as set forth in the attached re-vised Technical Specification pages (Appendix A to DPR-31 and DPR-41) and are as described below:
Pa e 3.1-5 In subsection 3.1.4 (in the first sentence) pCi/cc has been changed to "micro-curies per milliliter". This change was made to show the actual measured unit, milliliter (liquid measurement) as opposed to cubic centimeter (gaseous measure-ment).
A sentence was also added to the end of the first paragraph in subsection 3.1.4.
This eliminates the monthly testing of the degased reactor coolant activity unless the total activity, excluding tritium, is sufficiently high as to warrant a monthly test.
The monthly test results of the degased reactor coolant activity are normally so low that they provide data which is of little use.
Realistically, monthly testing is not necessary unless the activity approaches the level of 135/E, i.e.,
30 mCi/ml.
Since the specific activity predominately comes from the noble gases, we propose to test the noble gas activity monthly (see the proposed change to Table 4.1-2).
With the gross reactor coolant activity determined daily and the noble gas activity determined monthly, this reduces further the need to determine the total specific activity of the degased reactor coolant on a monthly basis.
HELPING BUILD FLORIDA
Mr. Edson G. Case, Acting Director Page Two September 19, 1974 The second paragraph of specification 3.1.4 has also been changed.
The addition of the second sentence in the first paragraph dictated the change to the second paragraph to avoid confusion as to which limit must be satis-fied before the reactor is required to be shutdown.
Pa e 3.1-6 In subsection 3.1.5, the first sentence in paragraph (d) has been changed.
This change removes the restriction which limits the oxygen concentration in the reactor coolant when the reactor coolant temperature is below 250F.
At low reactor coolant temperatures, when the reactor coolant is open to the atmosphere, the coolant oxygen content may reach saturation conditions.
How-ever, below 250F, the rate of corrosion is decreased to a point where control of the oxygen concentration is no longer necessary.
Pa e 4.1-1 Each surveillance frequency interval used in Section 4.0 is clearly defined by specifying the number of times per year the test is to be performed and the maximum time between tests.
Most of these definitions are adaptations-of the definitions which are listed in the existing Table 4.12-1.
Table 4.1-2 In item (1), the frequency of the radiochemistry analysis was changed from monthly to semi-annually and the name was changed to Isotopic Determination.
The isotopic determination and E determination were grouped together and a requirement added to increase the frequency of the E determination and the isotopic determination to monthly if the total reactor coolant activity, ex-cluding tritium, exceeded 30 pCi/Ml (see the proposed change to subsection 3.1.4, page 3.1-5).
With the E and isotopic determination required semi-
annually, the maximum time between tests was changed to 240 days to be consis-tent with the new frequency definitions (see the proposed change to Section 4.0, Page 4.1-1).
A requirement was also added to perform a noble gas isotopic determination monthly.
Since the activity of the reactor coolant is predominately due to the noble gases, a monthly isotopic determination will provide more useful data on reactor coolant activity.
A requirement to test for fluorides in the reactor coolant system was also incorporated into the table.
Subsection 3.1.5 specifies maximum fluoride, chloride and oxygen concentrations.
To properly limit the concentration requires testing the reactor coolant system for these elements.
Even though
Mr. Edson G. Case, Acting Director Page Three September 19, 1974 fluoride has not been included in the table, it has been included in the testing.
This change provides the necessary consistency between Table 4.1-2 and subsection 3.1.5.
In Item (5), the frequency of the rod drop time tests have been changed to require that the tests be performed only after maintenance has been per-formed on the control rods. It is not the intent of this specification to require the control rods to be tested following any maintenance but only maintenance involving the control rods.
In Item (9), the frequency of the refueling system interlocks check has been modified to clarify when the equipment check is to take place.
Punctionally checking the equipment prior to each refueling shutdown is not practical due to accessibility limitations in containment during operation.
It is more appropriate to check the equipment at each refueling shutdown prior to handling the fuel.
By reducing the time between the equipment check and the actual fuel handling operation, potential operational difficulties will be minimized.
In Item (10), the testing requirement has been eliminated when the accumulator is drained.
It is necessary to drain an accumulator in order to work on certain safety injection system components.
The length of time the accumulator may be required to be drained could conceivably interfere with the testing require-ment.
This change will prevent a conflict of this nature from occurring.
In Item (14), the testing requirement has also been eliminated when the steam generator(s) is (are) drained.
Like the accumulator, it may be necessary to drain the steam generator(s) for repair or inspection.
The length of time the steam generator(s) may be required to be drained could conceivably inter-fere with the testing requirement.
This change will prevent conflicts of this nature from occurring.
In Item (17), the maximum time between tests of the turbine stop and control valves, reheater stop and intercept valves has been added to more clearly define the testing frequency.
A provision was also made to'xempt the test from being required during shutdown.
The purpose of the test is to demonstrate that the valves will function as required under operating conditions.
Testing the valves while the reactor is shutdown would give no indication of their capability to function properly during reactor operation.
Table 4.12 Sheet 4
The frequency definitions were deleted because they are now stated at the beginning of Chapter 4 (see the proposed change to Section 4.0, Page 4.1-1).
Pa e B3.1-6 The bases have been made consistent with the proposed Technical Specifications.
Mr. Edson G. Case, Acting Director Page Pour September 19, 1974 Pa e B3.1-8 Addition)
No change has been made to the text.
The proposed change to Page B3.1-6 resulted in the addition of a new page.
We have reviewed these changes and have concluded that they do not involve any significant hazards considerations and there is reasonable assurance that the health and safety of the public will not be endangered.
Very truly yours, Robert E. Uhrig Vice President REU/DWR/cpc Attachment cc:
Mr. Jack R.
Newman
STATE OF FLORTDA)
)
COUNTY OF DADE
)
Robert E. Uhrig, being first duly sworn, deposes and says:
That he is a Vice President of Florida Power 6 Light Company, the Licensee herein; That he has executed the foregoing instrument; that the statements made in this said instrument are true and correct to the best of his knowledge, information and belief; and that he is authorised to execute the instrument of said Licensee.
Robert E. Uhrig Subscribed to and swor to before me this j'f day o
~/A.
,'974.
Notar Public in and for the County of de, State of Florida NOTARY PUBLIC, STATE of FLORIDA at lARGE MY COMA1ISSION EXPIRES APRIL 2, 1976 IIONDyao XHRg aahYMAhQ lLONONQ 4C444
e.
After shutdown, corrective action shall be taken before operation is resumed.
Above 2X of rated power, two leak detection systems of different principles shall be oper>>
able, one of which is sensitive to radioactivity.
The latter may be out of service for 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months provided two other systems are operable.
4 ~
MAXIMUMREACTOR COOLANT ACTIVITY The total specific activity of the reactor c'oolant due to nuclides with half-lives of more than 30
minutes, excluding tritium, shall not exceed'135/E microcuries per milliliterwhenever 'the reactor is critical or the average reactor coolant temperature is great'er than 500F.
When the'otal specific reactor coolant activity as defined above reaches 30 micro-curies per milliliter, the frequency of the isotopic determination and the E determin'ation shall be in-creased in accordance with Table 4.1-2.
If the limit of 135/E microcuries per milliliteris not satisfied, the reactor shall be shutdown and kl cooled to 500F or less within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .
E is the average of beta and gamma energy (Mev) per disintegration of the specific activity.
I3.1-5 6/21/74
5 ~
REACTOR COOLANT CHEMISTRY a.
The following are reactor coolant chemistry concentration maximum limits in ppm when coolant is above 250F:
Normal Limit Transient Limit Oxygen Chloride Fluoride 0.10 0.15 0.15 1.0 1.5 1.5 Corrective action shall be initiated if a normal limit is exceeded or if it is anticipated from trends that normal limits may be exceeded.
c, Cold shutdown shall be initiated if the transient limits are reached, or if the corrective action required in (b) above is ineffective in reducing transient concentrations within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .
If the maximum concentration of any, of V
the elements listed did not exceed the listed trarisient:;
value, operation may be resumed after corrective. action has been taken'therwise a safety review shall be made prior to startup.
d.
When reactor coolant is 250F or below only the chloride and fluoride limits in (a.)
above need be maintained.
If these limits are exceeded, the unit will be brought to cold shutdown and corrective action taken.
e.
Reactor coolant pump operation shall be permitted to ensure mixing during th6 corrective action phases specified above and shall be permitted at temper-atures 50F above the normal cold shutdown limit when bringing the reactor to cold shutdown or after reaching cold shutdown.
3.1-6
~.
4.0 SURVEILLANCE'E UIREMENTS Frequency definitions are as follows:
Each shift Daily Weekly Not less than 1080 times per annum maximum time. between tests 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months (1/2 day).
Not less than 360 times per annum maximum time between tests two days.
Not less than 48 times per annum maximum time between tests ten days.
Every Two Weeks Not less than 24 times per annum maximum Monthly Quarterly time between tests 20 days.
Not less than ten times per annum maximum time between tests 45 days.
- Not less than four times per annum maximum time between tests 120 days.
Semiannually
- Not less than two times per annum maximum Annually time between tests 240 days.
Not less than one time per annum maximum time between tests 450 days.
4.1 OPERATIONAL SAFETY REVIEW limiting conditions for operation.
~Ob ective:
To specify the minimum frequency and type of surveillance to be applied to equipment and conditions.
Calibration, testing, and checking of analog channels and testing of logic channels shall be performed as specified in Table 4.1-1.
Equipment and sampling tests shall be conducted as spec-ified in Table 4.1-2.
4.1-1 6/21/74
TABLE 4.1-2 MINIMUM FREQUENCIES FOR EQUIPMENT AND SAMPLING TESTS Check
~Fre uenc Max. Time Between Tests (Days) 1.
Reactor Coolant Samples Isotopic Determination Semiannually***
(Tl/2>30 Min) and E Deter mination 240 F Cl
& 0 **
Tritium Activity Gross B, y Activity (pCi/cc) 5/week Weekly 5/week 10 Boron Concentration Noble Gas Isotopic Determination 2/Week
'onthly 2.
Refueling Water Storage Tank Water Sample Boron Concentration Weekly 10 3.
Boric Acid Tank 4.
Boron Injection Tank 5.
Control Rods Boron 'Concentration Boron Concentration Rod drop times of all full length rods 2/Week Monthly 45 Each refueling shut-NA down and following control rod main-tenance Partial movement of full length rods Biweekly while critical 20 6.
Pressurizer Safety Valves 7.
Main Steam Safety Valves Set Point Set Point Each refueling shutdown f
Each refueling shutdown NA NA 8.
Containment Isolation Trip Functioning Each refueling shut-NA
down 9.
Refueling System Interlocks Functioning Each refueling shut-NA down prior to handling fuel
10. Accumulator Boron Concentration Monthly 45 (Not required when accumulator is drained)
I 6/21/74
D
t TABLE 4. 1-2 (COD)
MINIMUM FREQUENCIES FOR EQUIPMENT AND SAMPLING TESTS Check Precrpuene Max. Time Between Tests ll. Reactor Coolant System Leakage Evaluate Daily NA
12. Diesel Fuel Supply 13.
Spent Fuel Pit
14. Secondary Coolant I-131 Concentration Weekly*
(Not required when steam generator is drained) 10 Fuel Inventory Weekly 10 Boron Concentration Prior 'to Refueling NA
15. Vent Gas
& Particulates
16. Fire Protection Pump Power Supply t
17. Turbine Stop and Control Valves, Reheater Stop and Intercept Valves I-131
& Particulate Activity Operable Closure Weekly*
Monthly Monthly (Not required during shutdowns) 10 45 45 18e LP Turbine Rotor Inspection (w/o rotor disassembly)
V, MT, PT Every 5 years 6 years
'When activity exceeds 10% of spec, frequency shall be changed to Daily.
+ 0 need not be sampled when RCS temperature is less than 250F 2
+When the total reactor coolant activity, excluding tritium, exceeds 30 pCi/ml, the frequency shall be changed to monthly.
6/21/74
1
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TABLE 4.12-1 SHEET 4 OPERATIONAL'ENVIRONMENTALRADIOLOGICAL SURVEILLANCE PROGRAM (1)
(1)
(2)
(3)
(4)
(5)
Samples will be taken whenever biologically available.
Frequency definitions are in Section 4.0.
Analysis will be performed provided sufficient wet deposition occurs.
Gamma spectral and tritium analysis will be performed provided sufficient size liquid sample is collected.
A semi-annual survey will be conducted and any'hange reported to the AEC.
If milk producing herds are detected, a sampling program will be initiated.
6(21/74
continue.
Leakage source (ex. valve stem, pump shaft seal) shall be considered.
Make up capability and potential in-creased demand shall also be one of the evaluation factors.
Leakage in the containment will be detected by one or more
~
'f the following:
1.
The air particulate monitor 2.
The gas monitor 3.
The sump level recorder 4.
Changes in make up water requirements 5.
Visual inspection 6.
Audible detection Leakage to other systems will be detected by:
activity changes (ex. within the component cooling system), water inventory changes (ex. tank levels).
4.
Maximum Reactor Coolant Activit The maximum specified coolant activity of 135/E pCi/cc was selected on the basis that an uncontrolled accidental re-lease of reactor coolant to the environment would not give an excessive dose at the exclusion distance.
The frequency of the reactor coolant isotopic determination and the E determination will be increased when the specific coolant activity reaches 30 microcuriers per milliliter to minimize the potential for exceeding the 135/E limit.
The 30 microcuries per milliliteris calculated by using the most conservative average energy of the isotope with half lives B3.1-6 6/21/74
,greater than 30 minutes which are found in the reactor coolant system.
This energy, 4.58 MEU per disintegration (for Sodium 24), gives a limit of 135/E equal to 135/4.58 or 30 micro-curies per milliliter.
An uncontrolled release of activity to the environment could result from rupture of a steam generator tube which would
'llow reactor coolant to enter the secondary system.
The worst credible accident is considered to be a double-ended break of a single steam generator tube.
This accident has been analyzed, assuming the reactor coolant activity is at the specified limit.
The ma)or portion of the activity is noble gases, which were assumed released to the atmosphere from the air ejector or a safety valve.
Activity release was assumed to continue for one-half hour, at which time the reactor coolant system pressure decreases below the set-point of the secondary safety valves and the faulty steam generator is isolated.
During the 30 minutes, 70,000 lbs of reactor coolant would be released to the secondary system.
All the noble gas activity transferred to the steam gen-erator was assumed re'leased, while the iodine was assumed to partition between the liquid and vapor phases.
The resultant site boundary dose is approximately 0.25 rem whole body and approximately 2.5 rems to the thyroid, using the two-hour meteorological dispersion factor for the plant.
These doses are less than 1% of the guideline doses of 10 CFR 100.
5.
Maximum Reactor Coolant 0
en and Chloride Concentration By maintaining the reactor coolant chemistry within the limits specified, the integrity of the Reactor Coolant System is pro-tected.
B3.1-7 6/21/74
0
s If these limits are exceeded, measures can be taken to cor-rect the condition,. e.g.,
replacement of ion exchange resin or adjustment of the hydrogen concentration in the volume control tank, and further because of the time dependent nature of any adverse effects arising from concentrations in excess of the limits, it is unnecessary to shutdown immediately since the condition can be corrected.
Thus the period of 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months for corrective action to restore the concentrations within the limits has been established.
If the corrective action has not been effective at the end of the 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months period, then the reactor will be brought. to the cold shutdown condition and the corrective action will continue.
References (1)
FSAR Table 4.1-3
'(2)
FSAR Section 14.1.10 (3)
FSAR Section 4.2.8 B3.1-8 6/21/74
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P.O. BOX 3100 MIAMI,FLORIOA 33IOI FLORIDA POWER 8L LIGHT COMPANY September 19, 1974 Mr. Edson G. Case, Acting Director Directorate of Licensing Office of Regulation U.
S. Atomic Energy Commission Washington, D.
C.
20545
Dear Mr. Case:
Re:
Turkey Point Plant Units 3 and 4
Docket Nos. 50-250 and 50-251 Proposed Amendment to Facility 0 eratin Licenses DPR-31 and DPR-41 C9~~
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In accordance with 10 CFR 50.30, Florida Power
& Light Company submits herewith three signed originals and forty (40) conformed copies of a proposed amendment to Facility Operating Licenses DPR-31 and DPR-41.
This submittal replaces our corresponding June 21, 1974, request to amend the Facility Operating Licenses.
The changes are as set forth in the attached re-vised Technical Specification pages (Appendix A to DPR-31 and DPR-41) and are as described below:
Pa e 3.1-5 In subsection 3.1.4'~"(in the first sentence)
IICi/cc has been changed to "micro-curieg per milliliter". This change was made to show the actual measured unit, mill'A.'iter (liquid measurement) as opposed to cubic centimeter (gaseous measure-ment).
A sentence was also added to the end of the first paragraph in subsection 3.1.4.
This eliminates the monthly testing of the degased reactor coolant activity unless the total activity, excluding tritium, is sufficiently high as to warrant a monthly test.
The monthly test results of the degased reactor coolant activity are normally so low that they provide data which is of little use.
Realistically, monthly testing is not necessary unless the activity approaches the level of 135/E, i.e.,
30 mCi/ml.
Since the specific activity predominately comes from the noble gases, we propose to test the noble gas activity monthly (see the proposed change to Table 4.1-2).
With the gross reactor coolant activity determined daily and the noble gas activity determined monthly, this reduces further the need to determine the total specific activity of the degased reactor coolant on a monthly basis.
l 0787 HELPING BUILD FLORIDA
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Mr. Edson G. Case, Acting Director Page Two September 19, 1974 The second paragraph of specification 3.1.4 has also been changed.
The addition of the second sentence in the first paragraph dictated the change to the second paragraph to avoid confusion as to which limit must be satis-fied before the reactor is required to be shutdown.
Pa e 3.1-6 In subsection 3.1.5, the first sentence in paragraph (d) has been changed.
This change. removes the restriction which limits the oxygen concentration in the reactor coolant when the reactor coolant temperature is below 250F.
At low rea'ctor coolant temperatures, when the reactor coolant is open to the atmosphere, the coolant oxygen content may reach saturation conditions.
How-
ever, below 250F, the rate of corrosion is decreased to a point where control of the oxygen concentration is no longer necessary.
Pa e'4.1-1 Each surveillance frequency interval used in Section 4.0 is clearly'defined by specifying the number of times per year the test is to be performed and the maximum time between tests; Most of these definitions are adaptations of the definitions which are listed in the existing Table 4.12-1.
Table 4.1-2 In item (1), the frequency of the radiochemistry analysis was changed from monthly to semi-annually and the name was changed to Isotopic Determination.
The isotopic determination and E determination were grouped together and a requirement added to,increase the frequency of the E determination and the isotopic determination to monthly if the total reactor coolant activity, ex-cluding tritium, exceeded 30 pCi/Ml (see the proposed change to subsection 3.1.4, page 3.1-5).
With the E and isotopic determination required semi-
annually, the maximum time between tests was changed to 240 days to be consis-tent with the new frequency definitions (see the proposed change to Section 4.0, Page 4.1-1).
t A requirement was also added to perform a noble gas isotopic determination monthly.
Since the activity of the reactor coolant is predominately due to the noble 'gases, a monthly isotopic determination will provide more useful
(
data on reactor coolant activity.
A requirement to test for fluorides in the reactor coolant syst'm,was also incorporated into-the table.
Subsection 3.1.5 specifies maximum'fluoride, chloride and oxygen concentrations.
To properly limit the concentration requires testing the reactor coolant system for these elements. 'ven though
7
Mr. Edson G. Case, Acting Director Page Three September 19, 1974 fluoride has not been included in the table, it has been included in the testing.
This change provides the necessary consistency between Table 4.1-2 and subsection 3.1.5.
In Item (5), t'e frequency of the rod drop time tests have been changed to require that the tests be performed only after maintenance has been per-formed on the control rods. It is not the intent of this specification to require the control rods to be tested following any maintenance but only maintenance involving the control rods.
In Item (9), the frequency of the refueling system interlocks check has been modified to clarify when the equipment check 'is to take place.
Functionally checking the equipment prior to each refueling shutdown is not practical due to accessibility limitations in containment during operation.
It is more appropriate to check the equipment at each refueling shutdown prior to handling the fuel.
By reducing the time between the equipment check and the actual fuel handling operation, potential operational difficulties will be minimized.
In Item (10), the testing requirement has been eliminated when the accumulator is drained.
~ It is necessary to drain an accumulator in order to work on certain safety injection system components.
,The, length of time the accumulator may be required to be drained could conceivably interfere with the testing require-ment.
This ',change will prevent a'onflict of this nature from occurring.
1 In Item (14), the testing requirement has also been eliminated when the steam generator(s) is (are) drained.
Like the accumulator, it may be necessary to drain the steam generator(s) for repair or inspection.
The length of time the steam generator(s) may be required to be drained could conceivably inter-fere with the testing requirement.
This change will prevent conflicts of this nature from occurring.
In Item (17), the maximum time between tests of the turbine stop and'ontrol valves, reheater stop and intercept valves has been added to more clearly define the testing frequency.
A provision was also made to exempt the test from be'ing required during shutdown.
The purpose of the test is to demonstrate that the valves will function as required under operating conditions.
Testing the valves while the reactor is shutdown would give no indication of their capability to function properly during reactor operation.
Table 4.12-1 Sheet 4
The frequency definitions were deleted because they are now stated at the beginning of Chapter 4 (see the proposed change to Section 4.0, Page 4.1-1).
The bases have been made consistent with the proposed Technical Specifications.
J
Mr. Edson G. Case, Acting Director
, Page Four September 19, 1974 Pa e B3.1-8 (Addition)
No change has been made to the text.
The proposed change to Page B3.1-6 resulted in the addition of a new page.
We have reviewed these changes and have concluded that they do not involve any significant hazards considerations and there is reasonable assurance that the health and safety of the public will not be endangered.
Very truly yours, Robert E. Uhrig Vice President REU/DWR/cpc Attachment cc:
Mr. Jack R.
Newman
E I
1t
STATE OF FLORIDA)
)
COUNTY OF DADE
)
Robert E. Uhrig, being first duly sworn, deposes and says:
That he is a Vice President of Florida Power S Light Company, the Licensee herein; That he has executed the foregoing instrument; that the statements made in this said instrument are true and correct to the best of his knowledge, information and belief; and that he is authorized to execute the instrument of said Licensee.
Robert E. Uhrig Subscribed to and sworn to before me tais ~5 day o
l974.
Notar Public in and for the County of D de,"State of Florida fIOTARY PUBLIC, STATE of FLORIDAat LARGE
,;"""'MY~COhilhllSSION EXPIRES APRIL 2, 1976
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Dear Mr. Case:

Dear Mr. Case:

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