ML20127P163

Amends 172 & 171 to Licenses DPR-32 & DPR-37,respectively, Clarifying Definition & Requirements for Containment Integrity

ML20127P163
Person / Time
Site:	Surry
Issue date:	01/22/1993
From:	Berkow H Office of Nuclear Reactor Regulation
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ML20127P166	List: ML20127P163
References
NUDOCS 9302010202
Download: ML20127P163 (18)

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'JNITED STATES a

NUCLEAR F1L:GULATORY COMMISSION WASHINoTON D.C. 20668 o,s,*...*/

VIRGINIA ELECTRIC AND POWER COMPANY DOCKET N0. 50-28_Q SURRY POWER STAT 10tb___ UNIT NO._l AMEN 0 MENT TO FACILITY OPERATING LICENSE Amer.dment No.172 License No. DPR-32 1.

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

A.

The application for amendment by_ Virginia' Electric and Power Company (the licensee) dated June 1, 1992, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.

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

There 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 e,onducted in compliance with the Comission'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.

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. 2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.8 of Facility Operating License No. DPR-32 is hereby-amended to read as follows:

(B)

Technical Snecifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 172, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is offective as of its date of issuance and shall be implemented within 30 days.

FOR THE NUCLEAR REGULATORY COMMISSION M

He-bertN.Berkow, Dire,ctor Pr> ject Directorate 11-2 Division of Reactor Projects - I/11 Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: January 22, 1993 f

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UNITED STATES.

i NUCLEAR REGULATORY COMMISSION

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WASHINGTON, D.C. Miss

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EljtGINIA ELECTRIC AND POWER CQ fff81 3

i QQCKET NO 50-281 jiQRRY POWER STATION. UNIT IQJ -

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J AMENDMENT TO FACILI1V OPERATING LICENSE Amendment No.171

. License'No. DPR-37; 1.

The Nuclear Regul Atory Commission (the Commission) has found..that:

A.

The application for amendment =by Virginia Electric and Power-Company (thelicensee dated June 1, 1992, complies with the standards 'and requireme)nts of the Atomic Energy Act of:1954. as.

r amended (the Act) and the Commission's rules and regulations set:

forth'in 10 CFR Chapter I;-

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B.

The-facility will operate in conformity with the appitcation, the' provisions of the Act, and the-rules and-regulations of the' Commissioni.

C.

Thereisreasonableassurance(i)thattheactivitiesauthsizedi by this-amendment can be conducted without endangering-the healthi and' safety of the-publicaand -(11) that such activities.will be.

y-conducted in compliance with_ the Commission's regulations;-

t L D.

The issuance of this amendment will= not be inimical 1to the comon -

defense and security or to the. health and safety'of the-public; and E.

The. issuance of this amendment isLin accordance with 10 CFR Part',

51.of the Commission'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 3.B of Facility Operating License No. OPR-37 is hereby amended to rtad as follows:

(B)

Technical Soecifications The Techn' cal Specifications contained in Appendix A, as revised through Amendment No.171, 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 its date of issuance and shall be implemented within 30 days.

FOR THE NUCLEAR REGULATORY COMMISSION M/

dierbed N. Berkow, Director Project Directorate 11-2 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: January 22, 1993 1

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ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO. 172 TO FACILITY OPERATING LICENSE NO. OPR-32 AMENDMENT NO. 171 TO FACILITY OPERATING LICE,NSE NO. DPR-37 DOCKET NOS. 50-280 AND 50-281 Revise Appendix A as follows:

Remove Paaes Insert Phoes TS 1.0-4 TS 1.0-4 TS 1.0-5 TS 1.0-5 TS 3.8-1 TS 3.8-1 TS 3.8-2 TS 3.8-2 TS 3.8-3 TS 3.8-3 TS 3.8-4 TS 3.8-4 TS 3.8-5 TS 3.8-5 TS Figure 3.0-1 (2 pages)

TS Figure 3.8-1 (1 page)

TS 3.10-1 TS 3.10-1 TS 3.10-5 TS 3.10-5 TS 3.10-6 TS 3.10-6 TS 3.10-7 TS 3.10-7 TS 4.1-lb TS 4.1-lb r

4 5

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I' TS 1.04 1

4 2.

CHANNEL FUNCTIONAL TEST Injection of a simulated signal into an analog channel as close to the sensor as practicable or makeup of the logic combinations in a logic channel to verify that it is operable, induding alarm and.'or.

trip initiating action.

3.

CHANNEL CALIBRATION Adjustment of channel output such that it. responds, with:-

acceptable range and accuracy, to known values of the parameter -

which the channel measures. Calibration shall encompass the entire channel,' including equipment action, alarm,~or trip,and shall be deemed to include the CHANNEL FUNCTIONAL TEST.

4.

SOURCE CHECK-A source check shall be a qualitative assessment of radiation monitor response when the channel sensor Is-exposed to a radioactive source..

H.

CONTAINMENT INTEGRITY Containment integrity shall exist when:

a.-

The penetrations required to be closed during accident conditions are either:

U 1).

Capable of being closed by an OPERABLE containment automatic isolation valve system, or y

Amendment Nos.- '172 and 171 l

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4 TS 1.0 5 2)

Closed by at least one closed manual valve, bilnd flange, or deactivated automatic valve secured in ite. closed position except es provided in Specification 3.8.C. Non automatic or deactivated automatic containment isolation valves may be opened Intermittently for operational activities provided that the valves are under administrative control and are capable of being closed immediately,if required.

i b.

The equipment access hatch is closed and sealed; c.

Each airlock is OPERABLE except as provided in Specification 3.8.B, d.

The containment leakage rates are within the. limits of Specification 4.4, and '

e.

The sealing mechanism associated with each penetration (e.g.,

welds, bellows, or O tings)is OPERABLE.

l.

REPORTABLE EVENT A reportabie event shall be any of those conditions specified in.Sectionl 50.73 to 10 CFR Part 50.

Amendment Nos. 172 and 171

TS 3.81 3,6 CONTAINMENT Anolicability App!!cs to the integrity and operating pressure of the reactor containment.

Oblective l

To define the limiting opcrating conditions of the reactor contalnment.

SARClflCAlh10 A.

.QDNTAINMEN'T INTEGRITY 1.

CONTAINMENT INTEGRITY, as defined in TS Section 1.0, shall be maintained whenever the Reactor Coolant System temperature exceeds 200*F.

a.

Without CONTAINMENT INTEGRITY, re establish CONTAINMENT INTEGRITY In accordance with the definition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

b.

Otherwise, be in HOT SHUTDOWN within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

2.

The inside and outside isolation valves in the Containment Ventilation Purge System shall be locked, sealed, or otherwise secured closed whenever the Reactor Coolant System temperature exceeds 200*F.

3.

The inside and outside isolation valves in the containment vacuum ejector suction line shall be locked, sealed, or otherwise secured closed whenever the Reactor Coolant System temperature exceeds 200'F.

Amendment Nos.

172 and 171

TS 3.8-2 i

B.

Containmar'tllrlocks 1.

Each containment altiock shall be OPERABLE with both doors of the personnel alriock closed except when the airlock is being used 1

for normal transit entry and exit through the containment, then at y

least one airlock door shall be closed, n.

With one airlock or associated interlock inoperable, maintain the OPERABLE door closed and either restore the inoperable door to OPERABLE status or lock closed the OPERABLE door within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, b.

If the personnel airlock inner door or Interlock is Inoperable, the outer personnel airlock door may be opened for repair and retest of the inner door, if the Inoperability is due to the personnel airlock inner door seal exceeding the leakage test acceptance criteria, the outer personnel airlock door may be opened for a period of time not to exceed fifteen minutes with an annual cumulative time not to exceed one hour per year for repair and retest of the inner door seal.

c.

Otherwise, be in HOT SHUTDOWN within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

C.

Containment Isointion Valves 1.

Containment isolation valves shall be OPERABLEi With one'or more isolation valve (s) Inoperable, maintain at least one isolation i

valve OPERABLE in each affected penetration that is open and sithor:

a.

Restore the inoperable valve (s) to OPERABLE status within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, or b.

Isolate each affected penetration within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by use of at least one deactivated automatic valve secured in the isolation position, or i

Non automatic or deactivated automatic containment isolation valves may be opened on an intermittent basis under administrative control. The valves identified in TS 3.8.A.2 and TS 3.8.A.3 are excluded from this provision.

Amendment Nos.172 and 171

I 1

TS 3.6 3 J,l c.

Isolate each affected penetration within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by use of'at j

least one closed manual valve or blind flangeior j

1 d.

Otherwise, place the unN in HOT SHUTDOWN within the j

next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />, u

.)

D.

Internal Pramaura y

A 1.

. Containment air partial pressure shall be maintained within the j

acceptable operation range as identified in Figure 3.61 whenever j

the Reactor Coolant System temporature and pressure exceed

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4507 and 350_psig, respectively.

1 a.

With _ the containment alt-partial' pressure (outside the acceptable operation range, restore the alt partial pressure j

to within acceptable limits within_1 hour or be in at'least j

HOT SHUTDOWN within the next:6 hours'and in COLD ll SHUTDOWN within the following 30 hour3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />si j

I, M

.j CONTAINMENT INTEGRITY ensures that the release 'of radioactive materials i

from the containment will be restricted to those leakage paths;and associated leak rates assumed.in the'accide'nt analysis.' These restdctions, in, conjunction

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with the allowed leakage,- will limit th'e' site boundary ridiation dose to within the limits of 10 CFR 100 during accident conditions.

a

+

The operability of the containment isolation valves ensures that the containment atmosphere will'be' Isolated.from the outside environment inlthe event of!a q

release of radioactive material to the containment atmosphere or pressurization y

_o t e conta nment; _ The opening; of rnanuali.or deactivatedfautomat,1c fh!

i containment iso!ation valves on anVintermittent: basis'under administrative control includes the following considerations: (1);statiohing an operator, who is Y

L in constant; communication with-the control room,' at: the valve" controls,

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(2) instructing this operator to close tnese valves in anl accid' ent sitllation, land s.,

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,j Ameridment Nos. 172'and171L i

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TS 3.8 4 (3) assuring that environmental conditloas will not preclude access to close th-valves arxl 4) that this administrative or manual action will prevent the release of racloactMty outside the containment.

The Reactor Coolant System temperature and pressure being below 350'F and 450 psig, respectively, ersures that no significant amount of flashing steam will be formed and hence that there would be no significant pressure buildup in the containment 1 there is a loss of-coolant accident. Therefore, the containment intemal pre,sure is not required to be subatmospheric prior to exceeding 350'F and 450 psig.

The allowable value for the containment air partial pressure is presented in TS Figure 3.81 for service water temperatures from 25 to 92'F. The allowable value varies as shown in TS Figure 3.81 for a given containment average temperature. The RWST water shall have a maximum temperature of 45'F.

The horizontal limit lines in TS Figure 3.81 are based on LOCA peak calculated pressure critoria, and the sloped line is based on LOCA subatmospheric peak pressure criteria.

The curve shall be interpreted as follows:

The horizontal limit line designates the allowable air partial pressure value for the given average containment temperature. The horizontal limit line applies for service water temperatures from 25"F to the sloped line intersection value (maximum service water temperature).

From TS Figure 3.8-1, if the containment average temperature is 112'F and the service water temperature ic less than or equal to 83*F, the allowable air partial pressure value shall b6 less than or equal to 9.65 psia.- If the average containment temperature is 116'F and the service water temperature is less than or equ# to 88'F, the allowable air partial pressure value shall be less than or equal to 9.35 psia. These horizontal limit lines are a result of the higher allowable initial containment average temperatures and the analysis of the pump suction break.

Amendment Nos.

172 and 171

TS 3.8 5

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if the containment air partial pressure rises to a point above the allowable value the reactor shall be brought to the HOT SHUTDOWN condition. Il a LOCA occurs at the time the containment air partial pressure is at the maximum allowable value, the maximum containment pressure will be less than design pressure (45 psig), the containment will depressurize in less than t hour, and the maximum subatmosphedo peak pressure will be less than 0.0 psig.

If the containment air partial pressure cannot be maintained greater than or equal to 9.0 psla, the reactor shall be brought to the HOT SHUTDOWN l condition. The shell and dome plate liner of the containment are capable of j

withstanding an internal pressure as low as 3 psia, and the bottom mat liner is capable of withstanding an internal pressure as low as 8 psla.

References UFSAR Section 4.3.2 Reactor Coolant Pump UFSAR Section 5.2 Containment isolation UFSAR Section 5.2.1 Design Bases UFSAR Section 5.5.2 Isolation Design UFSAR Section 6.3.2 Containment Vacuum System Amendment Nos, 172 and 171

TS Figure 3.81 ALLOWABLE AIR PARTIAL PRESSURE SURRY POWER STATION UNITS 1 AND 2 l

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i ElGURE NOTATION TC - Containment average temperature FIGURE NOT.E3

1. Refueling Water Storage Tank temperature s 45'F.

2. Allowable operating air partial pressure in the containment is a function of seMee water temperature.

3. Horizontal lines designate allowable air partial pressure per given containment average temperature.

4. Each containment temperature line is a maximum for the given air partial pressure.

l Amendment Nos. 172 and 171

TS 3.101 3.10 REFUELING Anoticability Applies to operating limitations during REFUELING OPERATIONS.

Oblactive To assure that no accident could occur during REFUELING OPERATIONS that would affect pub llc health and safety, i

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,Soecifical!DR A.

During REFUELING OPERATIONS the following conditions are satisfied:

1.

The equipment access hatch and at least one door in the personnel airlocit shall be properly closed. For those penetratJons which provide a direct path from containment atmosphere to the outside atmosphere, the automatic containtnent ! solation valves shall be operable or the penetration shall be closed by a valve, blind flange, or equivalent.

2.

The Containment Ventilation Purge System and the area and airborne radiation monitors which initiate isolation of this system shall be tested and verified to be operable immediately prior to REFUELING OPERATIONS.

Amendments Nos.172 and 171 -

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TS 3.10 5 anren Detailed instructions, the above specified precautions, and the design of the fuel handl!ng equipment, which incorporates built in intorlocks and safety features, provide assurance that an accident, which v/ould result in a hazard to public health and safety, will not occur during unit REFUELING OPERATIONS.

When no change is being made in core geometry, one neutron detector is sufficient to monitor the core and permits maintenance of the out of function instrumentation. Continuous monhoring of radiation levels and neuton flux provides immediate indication of an unsafe condition.

Potential escape paths for fission product radioactivity within containment are required to be closed or capable of closure to prevent the release to the environment. However, since there is no potential for significant containment pressurization during refueling, the Appendix J leakage criteria and tests are not applicable.

The containment equipment access hatch, which is part of the containment pressure boundary, provides a means for moving large equipment and components into and out of the containment.

During REFUELING OPERATIONS, the equipment hatch is held in place with at least four approximately equally spaced bolts The containment airlocks, which are also part of the containment pressure boundary, provide a means for personnel access during periods when 1

CONTAINMENT INTEGRITY is required. Each alriock has a door at both ends.

The doors are normally interlocked to prevent simultaneous opening. During periods of unit shutdown when containmer.t closure is not required, the door interlock mechanism may be disabled, allowing both doors to remain open for extended periods when frequent containment entry is necessary.

During REFUELING OPERATIONS, containment closure is required. Therefore, the door interlock mechanism may remain disabled, but one airlock door must remain closed. The amergency escape airlock (trunk) may be removed from the equlpment access hatch during REFUELING OPERATIONS, provided the penetration is closed by an approved method which provides a temporary, atmospheric pressure ventilation barrier.

Amendment Nos. 172 and 17t'

TS 3.10 6 Containment high radiation levels and high airborne activity levels automatically stop and isolate the Containment Ventilation Purge System. The other containment penetrations that provide direct access from containment atmosphere to outside atmosphere must be isolated by at least one barrier during REFUELING OPERATIONS.

Isolation may be achieved by an OPERABLE automatic isolation valve, a closed valve, a blind flange, or by an equivalent isolation method. Equivalent isolation methods must be evaluated and may include use of a material that can p; ovide a temporary, atmospheric pressure ventilation barrier.

The fuel building ventilation exhaust is diverted through charcoal filters whenever refueling is in progress. At least one flow path is required for cooling and mixing the coolant contained in the reactor vessel so as to maintain a uniform boron concentration and to remove residual heat.

During refueling, the reactor refueling water cavity is tilled with approximately 220,000 gal of water borated to at least 2,300 ppm boron.

The boron concentration of this water, established by Specification 3.10.A.9,is sufficient to maintain the reactor suberitical by at least 5 % Ak/k in the COLD SHUTDOWN condition with all control rod assemblies inserted. This includes a 1% Ak/k and a 50 ppm boron concentration allowance for uncertainty. This concentration is also sufficient to maintain the core subcritical with no control rod assemblies inserted into the reactor. Checks are performed during the reload design and safety analysis process to ensure the K-effective is equal to or less than 0.95 for each core Periodic checks of refueling water boron concentration assure the proper shutdown marD n.

Specification 3.10.A.10 allows the Control Room i

Operator to inform the manipulator operator of any impending unsafe condition detected from the main control board indicators during fuel movement.

In addition to the above safeguards, interlocks are used during refueling to assure safe handling of the fuel assemblies. An excess weight interlock is provided on the lifting hoist to prevent movement of more than one fuel assembly at a time. The spent fuel transfer mechanism can accommodate only one fuel assembly at a time.

Amendment Nos. 172 and 171 l

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TS 3.10 7 l.

Upon each completion of core loading and installation of the reactor vessel head, specific mechanical and electrical tests will be performed prior to initial criticality.

The fuel handling accident has been analyzed based on the activity that could be released from fuel rod gaps of 204 rods of the highest power assembly

• with a 100 hour0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> decay period following power operation at 2550 MWt for 23,000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />. The requirements detailed in Specification 3.10 provide assurance that refueling unit conditions conform to the operating conditions cssumed in the accident analysis.

Detailed procedures and checks insure that fuel assemblies are loaded in the proper locations in the core. As ar, additional check, the movable incore detector system will be used to verify proper power distribution. This system is capable of revealing any assembly enrichment error or loading error which could cause power shapes to be peaked in excess of desiga value.

References UFSAR Section 5.2 Containment isolation UFSAR Section 6.3 Consequence Limiting Safeguards UFSAR Section 9.12 Fuel Handling System UFSAR Section 11.3 Radiation Protection UFSAR Section 13.3 Table 13.31 UFSAR Section 14.4.1 Fuel Handling Accidents UFSAR Supplement:

Volume I: Question 3.2

. ' od gas activhy from 204 rods of the highest power 15 x 15 assembly is

{,..dter than fuel rod gap activity from 264 rods of the highest power 17 x 17 demoristration assembly.

Amendment Nos.172 and 171

TS 4.1-1b F.

Containment Ventilation Purge System isolation valves:

1. The outside Containment Ventilaflon Purge System isolation valves and the isolation valve in the containment vacuum ejector suction ilne 4

outside containment shall be determined locked, sealed, or otherwise secured in the closed position at least once per 31 days.

2. The inside Containment Ventilation Pur0e System isolation valves and the isolation valve in the containment vacuum ejector suction line inside containment shall be verified locked, sealed,- or otherwise secured in the closed position each' COLD SHUTDOWN, but not

- required to be verified more than once per 92 days.

G.

Verify that each containment penetration 'not capable of being closed by OPERABLE automatic isolation valves and required to be closed during accident conditions is closed by manual valves, blind flanges, or deactivated automatic valves secured

• in the closed position at least once per 31 days. Valves, blind flanges, and deactivated automatic or manual valves located inside containment which are lockedi sealed, or.

otherwise secured in the closed position shall be verified closed during each COLD SHUTDOWN, but not required to be verified more than once per 92 days.

• Non-automatic or deactivated automatic valves may be opened on an Intermittent '

basis under administrative control. The valvss identified in TS 3.8.A.2 and TS 3.8.A.3 -

are excluded from this provision.

Arnendment Nos.172 and 171