Text

Amend 113 to License NPF-49,revising TSs to Increase Min Required Boron Concentration in Bat from 6,300 to 6,600 Ppm
	ML20083D063
Person / Time
Site:	Millstone
Issue date:	05/17/1995
From:	Mckee P; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20083D065	List: ML20083D063; ML20083D066;
References
	NUDOCS 9505240157
	Download: ML20083D063 (11)
	v • d • e

3 4

cd UNITED STATES y

g j

NUCLEAR REGULATORY COMMISSION WA$HINGTON, D.C. 30666-0001 NORTHEAST NUCLEAR ENERGY COMPANY. ET AL.

DOCKET NO. 50-421 MILLSTONE NUCLEAR POWER STATION. UNIT NO. 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.113 License No. NPF-49 1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by Northeast Nuclear Energy Company, et al. (the licensee) dated January 18, 1995, complies with the standards.and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance (1) 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; D.

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 Comission's regulations and all applicable requirements have been satisfied.

9505240157 950517 PDR ADOCK 05000423 p

PDR

2.

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 Facility Operating License No. NPF-49'is hereby amended to read as follows:

(2)

Technical Soecifications

~

The Technical Specifications contained in Appendix A, as revised through Amendment No.113

, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3.

This license amendment is effective as of the date of its issuance, to be implemented within 60 days of issuance.

FOR THE NUCLEAR REGULATORY C0tg4ISSION Phillip F. McKee, Direci.or Project Directorate I-3~

Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: flav 17,1995 O

_._,-.-.-ms-..,w.

7-

..r

0 ATTACHMENT TO LICENSE AMENDMENT NO.113 FACILITY OPERATING LICENSE NO. NPF-49 DOCKET NO. 50-423 Replace the following pages of the Appendix A, Technical Specifications, with the attached pages.

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

&mn Insert 3/4 1-1 3/4 1-1 3/4 1-3 3/4 1-3 3/4 1-8 3/4 1-8 3/4 1-17 3/4 1-17 3/4 1-18 3/4 1-18 3/4 9-1 3/4 9-1 3/4 10-1 3/4 10-1 B 3/4 1-3 8 3/4 1-3

j i

3/4.1 REACTIVITY COM1t0L SYSTEMS 3/4.1.1.1 B0 RATION CONTROL SillTD0tAl NARRIN - NODES 1 AM 2 LIMITING COMITION FOR OPERATION 3.1.1.1.1 The SHUTDOWN MARGIN shall be greater than or equal to 1.3% Ak/k for both four loop and three loop operation.

APPLICABILITY: MODES I and 2*.

ACTION:

With the SHUTDOWN MARGIN less than 1.3% Ak/k, immediately initiate and con-tinue boration at greater than or equal to 33 gpa of a solution containing greater than or equal to 6600 ppe boron or equivalent until the required l

SHUTDOWN MARGIN is restored.

SURVEILLANCE REQUIRENENTS 4.1.1.1.1 The SHUTDOWN MARGIN shall be determined to be greater than or equal to 1.3% Ak/k:

Within I hour after detection of an inoperable control rod (s) and at l

a.

least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter while the rod (s) is inoperable.

,If the inoperable control rod is imovable or untrippable, the above required SHUTDOWN MARGIN shall be verified acceptable with an increased allowance for the withdrawn worth of the immovable or untrippable control rod (s);

b.

When in MODE 1 or MODE 2 with 4 greater than or equal to 1 at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months by verifying that control bank withdrawal is within the limits of Specification 3.1.3.6; c.

When in MODE 2 with 4 less than 1, within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months prior to achieving reactor criticality by verifying that the predicted critical control rod position is within the limits of Specification 3.1.3.6; d.

Prior to initial operation above 5% RATED THERMAL POWER after each fuel loading, by consideration of the factors of Specification 4.1.1.1.2, with the control banks at the maximum insertion limit of Specification 3.1.3.6; and

See Special Test Exceptions Specification 3.10.1.

NILLSTONE - UNIT 3 3/4 1-1 Amendmont No. pp.113 0307

- ~.

1 l

3/4.1 REACTIVITY CGITROL SYSTDis 3/4.1.1 BORATION CONTROL SIRITDOW NARRIN - NDDES 3. 4 Alm 5 LOOPS FILLED LIMITING COM ITION FOR OPERATION i

3.1.1.1.2 The SHUTDOW MARGIN shall be greater than or equal to the limits shown in Figures 3.1-1, 3.1-3 and 3.1-4 for four loop operation and in Figure 3.1-2 for three loop operation.

APPLICABILITY: MbOES3,4and5 ACTION:

With'the SHUTDOW MARGIN less than the required value, immediately initiate J

and continue boration at greater than or equal to 33 gpm of a solution containing greater than or equal to 6600 ppe boron or equivalent until the required SHUTDOWN MARGIN is restored.

SURVEILLANCE REQUIRENENTS 4.1.1.1.2.1 The SHUTDOW MARGIN shall be determined to be greater than or equal to the required value:

a.

Within I hour after detection of an inoperable control rod (s) and at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter while the rod (s) is inoperable.

If the inoperable control rod is immovable or untrippable, the above required SHUTD0W NARGIN shall be verified acceptable with an increased allowance for the withdrawn worth of the immovable or untrippable control rod (s); and b.

At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by consideration of the following factors:

1)

Reactor Coolant System boron concentration, 2)

Control rod position, 3)

Reactor Coolant System average temperature, 4)

Fuel burnup based on gross thermal energy generation, 5)

Xenon concentration, and 6)

Samarium concentration.

4.1.1.1.2.2 Valve 3CHS-V305 shall be verified closed and locked at least once per 31 days, i

/

NI.L.LSTONE - UNIT 3 3/4 1-3 Amendment No. pp.113

1 MACTIV11Y CONTROL SYSTDIS I

SIENDotAl MARRIM - COLD SIEND0lAl - LOOPS 110T FILLED LINITING CO MITI0ll FOR OPERATI0ll I

i 3.1.1.2 The SHUTDOW MARGIN shall be greater than or equal to a)

.the limits shown in Figure 3.1-5 or b) the limits shown in Fi control system (CVCS) gure 3.1-4, with the chemical and' volume aligned to preclude reactor coolant system boron concentration reduction.

APPLICABILITY: MODE 5 LOOPS NOT FILLED ACTION:

a.

With the SHUTDOW MARGIN less than the above, immediately initiate and continue boration at greater than or equal to 33 gpa of a solution I

containing greater than or equal to 6600 ppe boron or equivalent until the required SHUTDOWN MARGIN is restored.

b.

With the CVCS dilution flow paths not closed and secured in position in accordance with Specification 3.1.1.2(b), immediately close and secure the paths or meet the limits shown in Figure 3.1-5.

SURVEILUUICE REQUIRENEES 4.1.1.2.1 The SHUTDOW MARGIN shall be determined to be greater than or equal to the above:

i a.

Within I hour after detection of an inoperable control rod (s) and at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter while the rod (s) is inoperable.

If the inoperable control rod is immovable or untrippable, the i

SHUTDOWN MARGIN shall be verified acceptable with an increased allowance for the withdrawn worth of the immovable or untrippable control rod (s); and b.

At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by consideration of the following factors:

1)

Reactor Coolant System boron concentration, 2)

Control rod position, 3)

Reactor Coolant System average temperature, 4)

Fuel burnup based on gross themal energy generation, NILLSTONE - UNIT 3 3/4 1-8 Amendment No. JP. 77,113 4

om

,-w

.u r-

. -,wn-v.--

im.

r--r~e-

e

= - - - -- - - - - - - - ~ - - - - - - - - ' - - - * ' ' ' - - - - - - - - - - - - - - - - - - - - - -

\\

REACTIVITY CONTROL SYSTEMS BORATED MTER SOURCE - SIRITDOW LIMITING COMITION FOR OPERATION 3.1.2.5 As a minimum, one of the following borated water sources shall be OPERA 8LE:

a.

A Boric Acid Storage System with:

1)

A minimum contained borated water volume of 6700 gallons, 2)

A boron concentration between 6600 and 7175 ppe, and 3)

A minimum solution temperature of 67'F.

b.

The refueling water storage tank (RWST) with:

1)

A minimum contained borated water volume of 250,000 gallons, 2)

A minimum boron concentration of 2700 ppa, and 3)

A minimum solution temperature of 40'F.

APPLICABILITY: N00ES 5 and 6.

ACTION:

With no borated water source OPERABLE, suspend all operations involving CORE ALTERATIONS or positive reactivity changes.

SURVEILLANCE REQUIREMENTS 4.1.2.5 The above required borated water source shall be demonstrated OPERABLE:

a.

At least once per 7 days by:

1)

Verifying the baron concentration of the water, 2)

Verifying the contained borated water volume, and 3)

Verifying the Boric Acid Transfer Pump Room temperature and the boric acid storage tank solution temperature when it is the source of borated water.

b.

At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by verifying the RWST temperature when it is the source of borated water and the outside air temperature is less than 35'F.

NILLSTONE - UNIT 3 3/4 1-17 Amendment No. pp,113 0310

.9 REACTIVITY CONTROL SYSTEMS B0 RATED WATER SOURCES - OPERATING LIMITING ColGITION FOR OPERATION 3.1.2.6 As a minimum the following borated water source (s) shall be OPERABLE as required by Specification 3.1.2.2:

a.

A Boric Acid Storage System with:

1)

A minimum borated water usable volume of 21,802 gallons, 2)

A boron concentration between 6600 and 7175 ppa, and l

3)

A minimum solution temperature of 67'F.

b.

The refueling water storage tank (RWST) with:

1)

A minimum contained borated water volume of 1,166,000

gallons, 2)

A boron concentration oatween 2700 and 2900 ppe, 3)

A minimum solution temperature of 40*F, and 4)

A maximum solution temperature of 50*F.

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTION:

a.

With the Boric Acid Storage System inoperable, restore the system to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and borated to a SHUTDOWN MARGIN equivalent to at least the limits as shown in Figure 3.1-4 at 200*F; restore the Boric Acid Storage System to OPERABLE status within the next 7 days or be in COLD SHUTDOWN within the next 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

b.

With the RWST inoperable, restore the tank to OPERABLE status within I hour or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

MILLSTONE - UNIT 3 3/4 1-18 Amendment No. JP, 77, 113 0310

- _. _ ~. _, _ _ _ _..

3/4.9 REFUELIM OPERATIONS e

3/4.9.1 BORON CONCElmtATION LIMITING COM ITION FOR OPERATION 3.9.1.1 The boron concentration of all filled portions of the Reactor Coolant System and the refueling canal shall be maintained unifone and sufficient to ensure that the more restrictive of the following reactivity conditions is met; either:

a.

A 4 of 0.95 or less, or b.

A boron concentration of greater than or equal to 2600 ppa.

Additionally, the CVCS valves of Specification 4.1.1.2.2 shall be closed and secured in position.

APPLICABILITY: NODE 6.*

ACTION:

With the requirements of the above specification not satisfied, a.

immediately suspend all operations involving CORE ALTERATIONS or positive reactivity changes and initiate and continue baration at greater than or equal to 33 gpa of a solution containing greater than or equal to 6600 ppe boron or its equivalent until 4 is reduced to less than or equal to 0.95 or the boron concentration is restored to greater than or equal to 2600 ppe, whichever is the more restrictive.

b.

With any of the CVCS valves of Specification 4.1.1.2.2 not closed **

and secured in position, immediately close and secure the valves.

SURVEILLANCE REQUIRENENTS i

4.9.1.1.1 The more restrictive of the above two reactivity conditions shall be determined prior to:

i a.

Removing or unbolting the reactor vessel head, and b.

Withdrawal of any full-length control rod in excess of 3 feet from its fully inserted position within the reactor vessel.

4.9.1.1.2 The boron concentration of the Reactor Coolant System and the refueling canal shall be determined by chemical analysis at least once per 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

4.9.1.1.3 The CVCS valves of Specification 4.1.1.2.2 shall be verified closed and locked at least once per 31 days.

4

The reactor shall be maintained in N00E 6 whenever fuel is in the reactor vessel with the vessel head closure bolts less than fully tensioned or with the head removed.

- Except those opened under administrative control.

l NILLSTONE - UNIT 3 3/4 9-1 Amendment No. pp, pp, pp. 113 0311 l

5 i

v--

,mr-_--_,

.m.-

r r,. -,,,-.-- -,- -

m.--

.m

4 3/4.10 SPECIAL TEST EXCEPTI0fts 3/4.10.1 SWfD0lAlllAltRIN 4

LIMITIIIS COMITI001 FOR OPERATI001 3.10.1 The SHUTDOWN MARGIN requirement of Specification 3.1.1.1 may be suspended for measurement of control rod worth and SHUTDOWN MARGIN provided reactivity equivalent to at least the highest estimated control rod worth is available for trip insertion from OPERABLE control rod (s).

APPLICABILITY: MODE 2.

ACTION:

a.

With any full-length control rod not fully inserted and with less than the above reactivity equivalent available for trip insertion, immediately initiate and continue boration at greater than or equal to 33 gpa of a solution containing greater than or equal to 6600 ppe boron or its equivalent until the SHUTDOWN MARGIN required by Specification 3.1.1.1 is restored.

b.

With all full-length control rods fully inserted and the reactor subcritical by less than the above reactivity equivalent, immedt-ately initiate and continue boration at greater than or equal to 33 gpa of a solution containing greater than or equal to 6600 ppa boron or its equivalent until the SHUTDOWN MARGIN required by Specification 3.1.1.1 is restored.

SURVEILLANCE REQUIREMENTS 4.10.1.1 The position of each full-length control rod either partially or fully withdrawn shall be determined at least once per 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

4.10.1.2 Each full-length control rod not fully inserted shall be demonstrated capable of full insertion when tripped from at least the 50% withdrawn position within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months prior to reducing the SHUTDOWN MARGIN to less than the limits of Specification 3.1.1.1.

I 1

h!LLSTONE - UNIT 3 3/4 10-1 Amendment No. 113 0312 j

2

1 REETIVITY CONROL SYSTEMS E

B0 RATION SYSTEMS (Continued)

+

MARGIN from expected operating conditions 'of equivalent to that required by Figure 3.1-5 after xenon decay and cooldown to 200*F.

The maximum boration capability boration volume) requirement is established to conservatively (minimum bound expected operating conditions throughout core operating life.

The initial RCS boron concentration is based on a minimum expected hot full power or hot zero power condition (peak xenon.

The final RCS boron concentration assumes ti.at the most reactive control ) rod is not inserted the core.

This set of conditions requires a minimum usable volume of 21,802 gallons of 6600 ppe borated water from the boric acid storage tanks or 1,166,000 gallons of 2700 ppe borated water from the refueling water storage tank (RWST).

A minimum RWST volume of 1,166,000 gallons is specified to be consistent with ECCS requirement.

With the RCS temperature below 200*F, one Boron Injection System is acceptable without single failure consideration on the basis of the stable reactivity condition of the reactor and, the additional restrictions prohibiting CORE ALTERATIONS and positive reactivity changes in the event the 1

single Boron Injection System becomes inoperable.

j

^

The limitation for a maximum of one centrifugal charging pump to be OPER-ABLE and the Surveillance Requirement to verify all charging pumps except the 1

required OPERABLE pump to be inoperable below 350'F provides assurance that a mass addition pressure transient can be relieved by the operation of a single PORV.

The boron capability required below 200*F is sufficient to provide a SHUTDOWN MARGIN of 1.3% Ak/k after xenon decay and cooldown from 200'F to i

140'F. This condition requires either a usable volume of 4100 gallons of 6600 ppe borated water from the boric acid storage tanks or 250,000 gallons of 2700 ppe borated water from the RWST.

The unusable volume in each boric acid storage tank is 1300 gallons.

The contained water volume limits include allowance for water not available because of discharge line location and other physical characteristics.

The limits on contained water volume and boron concentration of the RWST also ensure a pH value of between 7.0 and 7.5 for the solution recirculated within containment after a LOCA.

This pH band minimizes the evolution of iodine and mir.imizes the effect of chloride and caustic stress corrosion on mechanical systems and components.

The minimum RWST solution temperature for MODES 5 and 6 is based on analysis assumptions in addition to freeze protection considerations.

The minimum / maximum RWST solution temperatures for MODES 1, 2, 3 and 4 are based on analysis assumptions.

MIjl5 TONE-UNIT 3 8 3/4 1-3 Amendment JJ, pp, pp. 113 j

,y,,-..-.

~ y yy.,r.--ti

--- =-

**-e--

r---erm-

,--e

r-c

---^ *

--

ML20083D063

Text

Attachment:

Navigation menu

Search