ML17244A502

Amend 26 to License DPR-18,revising Tech Specs to Require Reactor Coolant Sys Overpressure Protection Mod

ML17244A502
Person / Time
Site:	Ginna
Issue date:	04/18/1979
From:	Ziemann D Office of Nuclear Reactor Regulation
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Shared Package
ML17244A503	List: ML17244A502 ML17244A505 ML17244A509
References
NUDOCS 7905090207
Download: ML17244A502 (24)

Text

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UNITEDSTATES NUCLEAR REGULATORYCOMMISSION WASHINGTON, D. C. 205$ 5 ROCHESTER GAS AND ELECTRIC CORPORATION DOCKET NO. 50-244 R.

E.

GINNA NUCLEAR POWER PLANT AMENDMENT TO PROVISIONAL OPERATING LICENSE 1.

The A.

B.

C.

D.

Amendment No. 26 License No.

DPR-18 Nuclear Regulatory Commission '(the Commission) has found that:

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I The application for amendment by Rochester Gas and Electric Corporation (the licensee) dated October 11, 1978 (transmitted by letter dated October 18, 1978),

as supported by the analysis submitted by letter dated July 29, 1977, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the CoIITIIission's rules and regulations set forth in 10 CFR Chapter I; The facility will operate in conformity with the application, the provisions of the Act, and the rules and 'regulations of the Colwlission'here is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; The issuance of this amendment will not be inimical to the common defense and. security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comnission's regulations and all applicable requirements have been satisfied.

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Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and paragraph 2.C(2) of Provisional Operating License No.

DPR-18 is hereby amended to read as follows:

(2)

Technical S ecifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 26

, are hereby incorporated in the license.

The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of the date of its issuance.

Attachment:

Changes to the Technical Specifications Date of Issuance:

April 18, lg7g FOR THE NUCLEAR REGULATORY COMMISSION E

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)Vv4vi Dennis L. Ziemann,'hief Operating Reactors Branch 82 Division of Operating Reactors

ATTACHMENT TO LICENSE AMENDMENT NO.

26 PROYISIONAL OPERATING LICENSE NO.

DPR-18 DOCKET NO. 50-244 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages.

The revised pages are identified by the captioned amendment number and contain vertical lines indicating the area of change.

REMOVE ili

3. 1-2

3. 1-4 3 ~ 2 3

3. 2-4

3. 3-4

3. 3-12

6. 9-10 INSERT 1ll 3.1-2 3.1-4 312"3 3.2-4 3.3-4 3.3-12 3.15-1 4.16-1 6.9-10

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TABLE OF CO<TEi>TS DEr I.va TIO;AS

2. 0 SAF'ETY LItvfITS A'AD 'h~iITPi'G SAFETY SYSTEM SET'I'IaXGS

2. 1-1 0

2, l 2.2 Safety L'mit, Reactor Core Safe 5'y Limit, R ea ctor Coolant System Pressure

2. 3 Limiting Safety System Settings, Protective Instru'mentation LIMITINGCO.'~DITIOYS FOR OPERA, TION

2. 1-1

2. 2-1

2. 3-1

3. 1-1 3,1 3.2 3o 3 3.4 3.5 3.6 3.7

3. S

3. 9 3, 10 3.!

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3. 13

3. 14 3.15 Reactor Coolant Sy

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3. l. 1.0 e

a tiona} Components

3. l. 2 Heatup an~i Co"ldoivn

3. 1, 3

%minimum Conditions for Criticality

3. 1.4 iviaximum Cool nt Activity

3. l. 5 Leal;age 3

1. C hiaxirnu-.n Reactor Coolant Oi.y"e",

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. Fluoride and Ch)uric." Concen'.: a.:sn CI:emical a..o Vol;:r.".e Cvntroi System Enic.g~ncy Core Cooling System.

Audi'.iary Cool'.n'~ Systems, Air Recircu',ation Fan Coolers, Containment

Spray, and C ha r coal Filter s Tu-bir e Cy" o Instrumentation Sys tern Contain:-.ent System "iu.':iiiary lectrica) Sy" te>ns Refuel~

Plant Ef '.cents C

.=.." l:oJ and Vo.':er D'.str'hution L!~its ann=.ro.

~o pv QQ aoj ln-Co;c jn~ ".. trum~nr"-t]('n Sr o. c

.=or os sors

!Snucoers

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Fire Su"cress-',on System Overpr essure Protection System 1-1

3. 1-1

3. 1-5

3. 1-17

3. 1-20

3. 1-25

3. 1-31 3

3. <<-1 3, 4-1

3. 5-1 3.6-<

3. 7-)

3. 8-I 3

3. 10-)

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3.14-1 3.15-1 Amendment No, 7$, 26

TABLE OF CONTENTS {coot.) O 4.0 SURVEILLANCE REQUIREMENTS 4.1 Operational Safety Review 4.2 Primary Component Tests 4.3 Primary System Testing Following Opening 4.4 Containment Tests 4.5 Safety Injection, Containment Spray and Iodine Removal Systems Tests 4.6 Emergency Power System Periodic Tests 4.7 Main Steam Stop Valves 4.8 Auxiliary Feedwater System 4.9 Reactivity Anomalies 4.10 Environm ntal Radiation Survey 4.11 Spent Fuel Pit Charcoal Adsorber Testing 4.12 Effluent Surveillance 4.13 Radioactive Ma erial Source Leakage Test 4.14 Shock Suppresso.s (Snubbers) 4.15 Fire Suppression System Test 4.16 Overpressure Protection System

5. 0 DES IGN FEATURES 5.1 Site 5.2 Containment Design Features 5.3 Reactor Design Features 5.4 Fuel Storage

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4.1-1 4.1-1

4. 2-1 4.3-1 4.4-1

4. 5-1 4,6-1

4. 7-1

4. 8-1 4.9-1 4.10-1

4. 11-1 4.12-1 4.13-1 4.14-1

4. 15-1 4..16-1 I

5.1-1

5. 2-1

5. 3-1 5.4-1 ii amendment No. g, 26

';1'.1;1'.1.1.

2

'd.

At leas one reactor coolant pump shall in operation for a planned transition from one Reactor Operating Mode to another invo'lving an increase in the boron concentration of the reactor

coolant, except for emergency boration.

I e.

A reactor coolant'ump shall not be started with one or more of the RCS cold leg temperatures

(< 330'F unless

1) the pressurizer water volume is less than 324 cubic feet (385 level) or 2) the secondary water temperature of each steam generator is less than 50'F above each of the RCS cold leg temperatures.

Steam Generator a.

One steam generator shall be capable of performing its heat transfer function whenever the average coolant temperatur e is above 350'F.

b.

The temperature difference across the tube sheet shall not exceed 100'F.

3.1.1.3 Safet Valves a.

At least one pressurizer code safetyvalve shall be operable whenever the reactor head is on the vessel.

b.

Both pressurizer code safety valves shall be operable whenever the reactor is critical.

Bases:

When the boron concentration of the reactor coolant system is to be reduced the process must be uniform to prevent sudden reactivity changes in the reactor.

Mixing of the reactor coolant will be sufficient to prevent a sudden increase in reactivity if at least one reactor coolant pump or one residual heat removal pump is running while the change is taking place.

The residual heat removal pump will circulate the primary system volume in approximately one half hour.

The pressurizer is of no concern because of the low pressurizer volume and because the pressurizer boron concentration will be higher than that of the rest of the reactor coolant.

When the boron concentration of the reactor coolant system is to be increased, the process must be uniform to prevent sudden reactivity increases in the reactor during subsequent startup of the reactor coolant pumps.

Mixing of the reactor coolant will be sufficient to maintain a uniform boron concentration if at least one reactor coolant pump is running while the change is taking place.

Emergency boration without a reactor coolant pump in operation is not prohibited by this specification.

Change No. fg Amendment No. g3, 26 3.1-2

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Prohibiting reactor coolant pump starts without a large void in the pressurizer or without a limited RCS temperature differential will prevent RCS overpressuri-zation due to expansion of cooler RCS water as it enters a warmer steam generator.

A 38% level in the pressurizer will accoranodate the swell resulting from a reactor coolant pump start with a RCS temperature of 140'F and steam generator secondary side temperature of 340'F, or the maximum temperature which usually exists prior to cooling the reactor with the RHR system.

The specification permits an orderly reduction in power if a reactor ~o~lant pump is lost during operation between 130 NMT and 50K of rated power.L2t Above 505 power, an automatic reactor trip will occur if either pump is lost.

The power-to-flow ratio will be maintained equal to or less than one which ensures that the minimum ONB ratio increases at lower flow since the maximum enthalpy rise does not increase.

Temperature requirements for the steam generator correspond with measured NDT for the shell and allowable thermal stresses in the tube sheet.

References (1)

FSAR Section 14.1.6 (2)

FSAR Section 7.2.3 Amendment No. 26 3.1-4

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C.

One boric acid tank may be out of service provided a minimum of 2,000 gallons of a 12% to 13% by weight boric acid solution at a temperature of at least 145'F is contained in the operable tank and provided that the tank is restored to operable status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

d.

One channel of heat tracing may be out, of service provided it is restored to operable status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />".

3.2.4 Basis

whenever the reactor coolant system is

> 200'F and is being cooled by the RHR system and the overpressure protection system is not operable, at least one charging pump shall be demonstrated inoperable at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by verifying that the control switch is in the pull-stop position.

The chemical and volume control system yy~vides control of the reactor coolant system boron inventory.

This is normally accomplished by using either one of the three'harging pumps

.in series with one of the two boric acid pumps.

An alternate method of boration will be to use the charging pumps directly from the refueling water storage tank.

A third method will be d pressurize and use the safety injection pumps.

There are'=

two sources of borated water available for injection thr g

ou h three different paths.

(1)

The boric acid transfer pumps can deliver the boric aczd tank contents (12% concentration of boric acid) to the charging pumps.

(2)

The char'ging pumps can take suction from the refueling water storage tank.

(2,000 ppm boron solution)

(3)

The safety injection pumps can take their suctions from either the boric acid tanks or the refueling water storage tank.

The quantity of boric acid in storage from either the boric acid tanks or the refueling water storage tank is~sufficient to borate the reactor coolant in order to reach cold shutdown at any time during core life.

Approximately 1SOO gallons of the 12% to 13%

soluti of boric acid are required to meet cold'shutdown condi-tions.~

Thus, a mi'nimum of 2000 gallons in,,the boric acid tanks is specified.

An upper concentration limit of 13% boric acid in the tank is specified to maintain solution solubility at. the speci-fied low temperature limit of 145'F.

Two channels of heat tracing are installed on lines normally containing concentrated boric acid solution to maintain the specified low temperature limit.

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/'mendment No.

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Placing a charging pump in pull-stop whenever the reactor coolant system temperature is

> 200'F and is being cooled by RHR without the ove+ressure protection system operable will prevent inadvertgP) overpressurization of the RHR system should letdown be terminated.

References:

(1)

FSAR, Section 9.2 (2)

FSAR, Page 9.2-37 (3)

L. D. White, Jr. letter to A. Schwencer, NRC, dated February 24, 1977 Amendment No.

26

d.

e.

(ii) The two reactor coolant drain tank pumps shall be tested and their operability demon-strated prior to initiating repairs of the inoperable residual heat removal pump.

One residual heat exchanger may be out of service for a pe'riod of no more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Any valve required for the functioning of the safety injection or residual heat, removal systems may be inoperable provided repairs are completed within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

Prior to initiating repairs, all valves in the systems that provide the duplicate function shall be tested to demonstrate operability.

3.3.1.3 f.

Power may be restored to any valve referenced in 3.3.1.1 g for the purposes of valve testing providing no more than one such valve has power restored and provided"testing is completed and power removed within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

Except during diesel generator load,and safeguard sequence testing or when the vessel head is removed or the steam generator manway is open no more than one safety injection pump shall'be operable whenever the temperature. of one or more of the RCS cold legs is 330'F.

3.3.1.3.1 3.3.2

'.3.2.1 Mhenever only one safety injection pump may be operable by 3.3.1.3 at least two of the three safety injection pumps shall be demonstrated inoperable a

minimum of once per twelve hours by verifying that the control switches are in the pull-stop position.

Containment Coolin and iodine Removal The reactor shall not be made critical except for low temperature physics tests, unless the following condi-tions are met:

b.

C.

The spray additive tank contains not less than 4500 gallons of solution with a sodium hydroxide concentration of not less than 30% by weight.

II At least two containment spray pumps 'are operable.

At least three fan cooler units are operable.

Amendment Ho. ~

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( 6)( 7)

The facility has four service water pumps.

Only one is needed during the injection phase, and two are required during the (8) recirculation phase of a postulated loss-of-coolant accident.

I The limits for the accumulator pressure and volume assure the re-quired amount of water injection during an accident, and are based on values used for the accident analyses.

The indicated level of 50% corresponds to 1108 cubic feet of water in the accumulator and the indicated level of 82% corresponds to 1134 cubic feet.

The limitation of no more thin one safety injection pump to be operable and the surveillance requirement to verify that, two safety injection pumps are inoperable below 330'F provides assurance that a mass addition pressure transient can be relieved by the operate.on of a single PORV.

Rci'ct cnc:cs I

(1)

CESAR Section 9. 3

{2)

CESAR Section 6. 2 (3)

FSrl R Section

6. 3 4

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FSAR Section l-i. 3. 5 rr

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FSAR Section

1. 2

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FSAR Section 9. 3 (7)

CESAR Section ld. 3

{8)

FSrXR Section Q. 4 3.3-12 Amendment No. W 26

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3.15' Ove ressure Protection S stem r~ld>> 1 Applies whenever the temperature of one or more of the RCS cold legs is

< 330'F.

Ob'ective 3.15.1 To prevent overpressurization of the reactor coolant system.

a

'f't least one of the following overpressure protection systems shall be operable:

a.

Two pressurizer power operated relief valves (PORVs) with a liftsetting of

< 435 psig, or b.

A reactor coolant system vent, of ) 1.1 square inches.

3.15.1.1 With one PORV inoperable, either restore the inoperable PORV to operable status within 7 days or depressurize and vent the RCS through a 1.1 square inch vent(s) within the next 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />; maintain the RCS in a vented condition until both PORVs have been restored to operable status.

3.15.1.2 3.15.1.3 With both PORUs inoperable, depressurize and vent the RCS through a 1.1 square inch vent(s) within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />; maintain the RCS in a vented condition until both PORVs have been restored to operable status.

Use of the overpressure protection system to mitigate a

RCS pressure transient shall be reported in accordance with 6.9.3.

Basis The operability of two pressurizer PORVs or an RCS vent opening of greater than 1.1 square inches ensures that the RCS will be protected from pressure transients which could exceed the limits of Appendix G to 10 CFR Part 50 when one or more of the RCS cold legs are

< 330'F.

Either PORV has adequate relieving capability to protect the RCS from overpressurization when the transient is limited to either (1) the start of an idle RCP with the secondary water temperature of the steam generator

< 50'F above the RCS cold leg temperature or (2) the start of ~1~afety injection pump and its injection into a water solid RCS.

References:

(1)

L. D. White, Jr. letter to A. Schwencer, NRC, dated July 29, 1977 Amendment -;Ho. 26 3.15-1

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Ove ressure Protection S stem A licabilit :

4.16.2 Applies to the reactor coolant system overpressure protection system.

~b'o verify that, the overpressure protection system will function properly if needed.

H Each PORV shall be demonstrated operable by:

Performance of a channel functional test on the PORV actuation channel, but excluding valve opera-tion, within 31 days prior to entering a condition in which the PORV is required operable and at least. once per 31 days thereafter when the PORV is required operable.

b.

Performance of a channel calibration on the PORV actuation channel at least once per 18 months.

c.

Verifying the PORV isolation valve is open at least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> when the overpressure protection system is required to be operable.

The RCS vent(s) shall be verified to be open 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 vent(s) is being used for overpressure protection except when the vent pathway is provided with a valve which is locked,

sealed, or otherwise secured in the open position.

Then verify these valves open at least once per 31 days.

Anendment No. 26 4.16-1

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(2) 0 Annually:

A tabulation on an annual basis of the number of station, utility and other per-sonnel (including contractors) receiving ex-posures greater than 200 mrem/yr and their associated man rem exposure according to work and job functions, e;g., reactor operations and surveillance, inservice inspection, routine maintenance, special maintenance (describe maintenance),,

waste processing, and refueling.

The dose assignment to various duty functions may be estimates based on pocket dosimeter, TU), or film badge measure-ments.

Small exposures totalling less than 20% of the individual total dose need not be accounted for.

In the aggregate, at least S0% of the total whole body dose received from external sources shall be assigned to specific major work functions.

(NOTE:

This tabulation supplements the re-quirements of Section 20.407 of 10 CFR Part 20.)

d.

Reactor Overpressure Protection System Operation In the event either the PORVs or the RCS vent(s) are used to mitigate a

RCS pressure transient, a

Special Report shall be prepared and submitted to the Commission within 30 days.

The report shall describe the circumstances initiating the transient, the effect of the PORUs or vent(s) on the transient and any other corrective action necessary to prevent recurrence.

Amendment No. 26 6.9-10

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