ML18227C827

Letter Submitting Three Signed Originals and Forty Conformed Copies of Request to Amend Facility Operating License DPR-31 and DPR-41

ML18227C827
Person / Time
Site:	Turkey Point
Issue date:	06/21/1974
From:	Robert E. Uhrig Florida Power & Light Co
To:	O'Leary J US Atomic Energy Commission (AEC)
References
Download: ML18227C827 (28)

Text

AEC DISTRI.'ITION FOR PART 50 DOC'.KT MATERI'TEt fPORARY FORH)

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Florida Power 6 Light Company Hiami, Fla.

33101 Mr. R.E. Uhrig

'6-21-74 6-28-74 DATE OF DOC DATE REC'D LTR TWX OTMR

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J.F. O'eary ORIG 3 signed CC 'THER SENT AEC PDR XXX SENT LOCAL PDR CLASS UNCLASS XXX PROP INFO INPUT XXX NO S REC'D 40 DOCKET NO:

0-25 251 DESCRIPTION:

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PLANT NAME.

Turkey Point 3 6 4 ENCLOSURES:

Proposed changes to tech specs forthe Turkey

, Point 3 6 4 Nuclear Facility.....

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Mr. John F. O'eary, Director, Directorate of Licensing Office of Regulation U.

S. Atomic Energy Commission Washington, D.

C.

20545

Dear Mr. O'eary:

Re:

Turkey Point Plant Units 3

& 4 Docket Nos.

50-250 6 50-251 Proposed Amendment to Facility.

0 er'at'in L'i'c'e'n's'e's'PR-316'PR-41 In accordance with 10 CFR 50.59, Florida Power 6 Light Company submits herewith thr'ee signed originals and forty (40) conformed copies of a proposed amendment to Facility Operating Licenses DPR-31 6c DPR-41.

The "changes are as set forth in the revised Technical Specifications'ages (Appendix A to DPR-31 6 DPR-41) and are as described below:

In specification 3.1.4 (in the first sentence)

@CD./cc has been changed to "microcuries per milliliter". This change was made to show the actual measured unit, milliliter (liquid measurement) as opposed to cubic'entimeter (gaseous measurement).

A sentence was also added to the end of the first paragraph in Specification 3.1.'4.

This change reduces the reactor coolant sampling frequency without degrading the 'safety of the plant.

It eliminates 'the monthly sampling of the reactor coolant activity unless the total activity, excluding tritium, is sufficiently high 'as to warrant the sampling frequency.

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. satisfied before the reactor is required to be shut-down.

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~ ~ 1 Mr. John F. O'eary June 21, 1974 Pa e 3.1-6 In specification 3.1.5, the first sentence in paragraph (d) has been changed.

Thi;s '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.

However, below 250F, the rate 'of corrosion is decreased to a point wher'e control of the oxygen concentration is no longer necessary.

4: 1-1 More rigorous definitions for surveillance requirements have been added.

These definitions were previously applicable only to the Operational Environmental Radiological Surveillance Program.

Table'.1-2 In item (1), the frequency of the radi<<hemistry 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 change the frequency of the f determination and the isotopic determination to monthly if the total reactor coolant activity, excluding tritium, exceeded 30 pCi/ml.

The maximum time betyee'n E det'ermination and isotopic,det'ermination was changed to 240, days to be consistent with the new frequency definitions (see 'the 'proposed change to,Section 4.0, Page 4.1-1).

A require-ment was added to perform noble gas isotopic determination monthly.

The requirement to check for fluorides in.the reactor coolant system was also incorporated into the table.

In item (5), the frequency of the rod drop time tests has been changed.

This change clarifies the testing requirements.

In item (9), the frequency of the refueling system interlocks check has been modified to clarify when the equipment check is to take place.

In items (10) and (14), the, sampling requirements have been eliminated when the accumulators and steam generators, respectively, have bee'n drained.

In item (17), the maximum time between tests of the turbine stop and control. valves, reheater'top and intercept valves has been added.

A provision was also made to exempt the test from being required during shutdown.

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Mr. John F. O'e June 21, 1974 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).

~3; I:-6 The bases have been made consistent with the proposed Technical Specifications.

Pa e'3'.'1'-'8'{'A'ddit'i'on)

No change has.been'ade

'to the'ext.

NOTE:

The proposed change to Page B3.1-6 shifted the contents of Page B3.1-7 to the point wher'e 'the'ddition of a new page was required.

These changes have been reviewed by the Plant Nuclear Safety Committee and the Company Nuclear Review Board.

These groups have independently det'ermined that the 'changes, do not degrade but, in fact, improve the 'safety of the 'facility.

Very uly yours,'obert,E.

Uhrig Vice 'President REU:nch

'ttach.

cc:

Mr. Jack R.

Newman

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STATE OF FLORIDA )

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COUNTY OF DADE

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Robert E. Uhrig, being first duly sworn, deposes and says:

That he 'is a Vice Pres'ident of Florida Power"6 Li.'ght,Company, the Licensee herein; That he has "executed the foregoing instrument; that the statements made 'in this said instrumen't are true 'and correct to the bes't of his knowledge,'nformation and belie'f; and that he's authorized to execute 'the 'instrument of said Licensee.'

ert rig Subs'cribed to and sworn.to before me this'ay of a

, 1974.

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'of Dade,'tate of Florida

,. IfOTSRY PUBLIC, STATE of FLORIOA at LARGE s....gY;COMMISSION EXPIRES APRIL 2p 191'6

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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 <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> provided two other systems are operable.

4.

MAXIMUMREACTOR COOLANT ACTIVITY The total specific activity of the reactor coolant 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 greater than 500F.

When the total specific reactor coolant activity as defined above reaches 30 micro-curies per milliliter, the frequency of the isotopic determination and the E determination 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 cooled to 500F or less within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

• E is the average of beta and gamma energy (Mev) per disintegration of the specific activity.

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 0.15 1.0 1.5 1.5 b.

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 <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

If the maximum concentration of any, o'

the elements listed did not exceed the listed trari'sient; value, operation may be resumed after corrective. action has been taken.

Otherwise a safety review shall be made prior to startup.

d.

When reactor coolant is 250F or below only the il 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 the 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 6/21/74

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4.0 SURVEILLANCE'RE 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 <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> (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.

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 Betwee'n Tests (Days) 1.

Reactor Coolant Samples Isotopic Determination Semiannually***

(Tl/2>30 Min) and E Deter-mination 240 F Cl

@ 0 **

Tritium Activity Gross 9, y Activity (pCi/cc)

,5/we'ek Weekly 5/week 10 Boron Concentration Noble Gas Isotopic Determination 2/Week Monthly 45 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 6.

Pressurizer Safety Valves Partial movement of full length rods n

Set Point Biweekly while critical Each refueling shutdown 20 NA 7.

Main Steam Safety Valves Set Point Each refueling shutdown 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

'0.

Accumulator Boron Concentration Monthly 45 (Not required when accumulator is drained) 6/21/74

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TABLE 4.1-2 (CONT'INIMUM FREQUENCIES FOR EQUIPMENT AND SAMPLING TESTS Check

~Fre cene Max. Time Between Tests

11. Reactor Coolant System Leakage

Evaluate, Daily NA

12. Diesel Fuel Supply

13. Spent Fuel Pit

14. Secondary Coolant Fuel Inventory Boron Concentration I-131 Concentration Weekly 10 Weekly*

10 (Not required when steam generator is drained)

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 I

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 l

• '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

TABLE 4.12-1 SHEET 4 OPERATIONAL ENVIRONMENTAL RADIOLOGICAL SURVEILLANCE PROGRAM (1)

(1)

Samples will be taken whenever biologically available.

(2)

Frequency definitions are in Section 4.0.

(3)

Analysis will be performed provided sufficient wet deposition occurs.

(4)

Gamma spectral and tritium analysis will be performed provided sufficient size liquid sample is collected.

(5)

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)21I74

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 of 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).

Maximum Reactor Coolant Activit The maximum specified coolant activity of 135/E pCi/cc was selected on t'e 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 t'e E determination will be increased when the specific coolant activity reaches 30 microcuriers per milliliterto 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

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greater than 30 minutes which are found in the reactor, coolant system.

This energy, 4.58 MEV 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 coul'd result from rupture of a steam generator tube which would allow 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 major 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

released, 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 S

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

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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 <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 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 <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 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