ML20198G615

Amend 154 to License NPF-49,modifying List of Valves That Can Be Opened in Modes 1 Through 4

ML20198G615
Person / Time
Site:	Millstone
Issue date:	12/18/1997
From:	NRC (Affiliation Not Assigned)
To:
Shared Package
ML20198G619	List: ML20198G615 ML20198G622
References
NUDOCS 9801130079
Download: ML20198G615 (10)

Text

.

4 ps* "%g#

e t

UNITED STATES o

i j

,, j NUCLEAR REGULATORY COMMISSION C

WASHINGTON. D.C. 20665 0001

\\...../

NORTHEAST NUCLEAR ENERGY COMPANY. ET AL.

DOCKET NO. 50-423 MILLSTONE NUCLEAR POWER STATION. UNIT NO. 3 MENDMENT TO FACILITY OPERATING LICENSE Amendment No. 154 License No. NPF-49 1.

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

A.

The apolication for amendment by Northeast Nuclear Energy Company, et al. (the licensee) dated October 7,1997, as supplemented December 17, 1997, 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 (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the puolic, 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 Commission's regulations and all applicable requirements have been satisfied.

9001130079 971210 DR ADOCK 050004 3

4 f' 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:

s (2)

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

154, 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 COMMISSION PhillipF.[?

McKee Deputy Director for Licensing Special Projects Office Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance:

December 18, 1997

-~ - -

ATTACHMENT TO LICENSE AMENDMENT NO.154 FACILITY OPERATING LICENSE NO. NPF-49 DOCKET NO. 50-421 Replace the following anges of the Appendix A, Technical Specifications, with the attached pages.

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

kemove Insert 3/4 6-1 3/4 6-1 3/4 6-2 3/4 6-2 3/4 6-3 3/4 6-3 3/4 6-5 3/4 6-5 3/4 6-6 3/4 6-6 B 3/4 6-1 B 3/4 6-1 B 3/4 6-la B 3/4 6-la

' 3/4.'3 CONTAINMENT SYSTEM 1 3/4.8.1 PRIMARY CONTAINNENT CONTAINMENT INTEGRITY LIMITING CONDITION FOR OPERATION 3.6.1.1 Primary CONTAINMENT INTEGRITY shall be maintained.

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

ACTION:

Without primary CONTAINMENT INTEGRITY, restore CONTAINMENT INTEGRITY within I hour or be in at least HOT STANDBY 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 />.

SURVEILLANCE REQUIREMENTS 4.6.1.1 Primary CONTAINMENT INTEGRITY shall be demonstrated:

a.

At least once per 31 days by verifying that all penetrations

• not capable of being closed by OPERABLE containment automatic isolation valves or operator action during periods when containment isolation valves are opened under administrative control,** and required to be cloLed during accident conditions are closed by valves, blind flanges, or deactivated automatic valves secured in their positions.

b.

By verifying that nch containment air lock is in compliance with the requirements or Specification 3.6.1.3; and c.

After each closing of each penetration subject to Type B testing, except the containment air locks, if opened following a Type A or D test, by leak rate testing the seal with gas at a pressure greater than or equal to P., 38.57 psig, and verifying that when the measured leakage rate for these seals is added to the leakage rates determined pursuant to Specification 4.6.1.2d for all other Type B and C penetrations, the combined leakage rate is less than 0.60 L,.

Except valves, blind flanges, and deactivated automatic valves which are located inside the containment and are locked, sealed, or otherwise secured in the closed position. These penetrations shall be verified closed during each COLD SHUTDOWN except that such verification need not be performed more often than once per 92 days.

The following valves may be opened on an intermittent basis under administrative control. Manual valves 3 SSP *V13, 3 SSP *V14, 3HCS*V2,

-3HCS*V3, 3HCS*V9, 3HCS*V10, 3HCS*V6, 3HCS*V13, 3CHS*V371, 3 MSS *Vd85, 3HSS*V886, 3 MSS *V887.

Remote manual valves 3RHS*MV8701A, 3RHS*MV8701B, 3RHS*MY8702A, 3RHS*MV8702B.

gNLSTONE - UNIT 3 3/46-1 Amendment No. M 154

CONTAIMENT SYSTEMS CONTAIMENT LEAKAGE LINITING CONDITION FOR OPERATION 3.6.1.2 Containment leakage rates shall be limited to:

a.

An overall integrated leakage rate of less than or equal to L.,

0.3% by weight of the containment air per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at P., 38.57 psig; !

b.

A combined leakage rate of less than 0.60 L, for all penetrations and valves subject to Type B and C tests, when pressurized to P,; and c.

A combined leakage rate of less than or equal to 0.042 L, for all penetrations that are Secondary Containment bypass leakage paths when pressurized to P,.

APPLICABILITY:

MODES 1, 2, 3, and 4.

ACTION:

With the measured overall integrated containment leakage rate exceeding 0.75 L., or the measured combined leakage rate for all penetrations and valves subject to Type B and C tests exceeding 0.60 L., or the combined bypass leakage rate exceeding 0.042 L., restore the overall integrated leakage rate to less than 0.75 L., the combined leakage rate for all penetrations subject to Type B and C tests to less than 0.60 L., and the combined bypass leakage rate to less than 0.042 L, prior to increasing the Reactor Coolant System temperature above 200*F.

SURVEILLANCE REQUIREMENTS 4.6.1.2 The containment leakage rates shall be demonstrated at the following test schedule and shall be determined in conformance with the criteria specified in Appendix J of 10 CFR Part 50 using methods and provisions of ANSI N45.4-1972 (Total Time Method) and/or ANSI /ANS 56.8-1981 (Mass Point Method):

a.

Three Type A tests (Overall Integrated Containment Leakage Rate) shall be conducted at approximately equal intervals during shutdown at a pressure greater than or equal to P., 38.57 psig, during each 10-year service period, b.

If any periodic Type A test fails to meet 0.75 L., the test schedule for subsequent Type A tests shall be reviewed and approved by the Commission.

If two consecutive Type A tests fail to meet 0.75 L.,

a Type A test shall be performed at least every 18 months until two consecutive Type A tests meet 0.75 L, at which time the above test schedule may be resumed; MILLSTONE - UNIT 3 3/4 6-2 Amendment No. 77,77,77,//J, N *o 777,154

CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)

~

c.

The accuracy of each Type A test shall be verified by a supplemental test which:

1)

Confirms the accuracy of the test by verifying that the supple-mental test results, L, minus the sum of the Type A and the superimposed leak, L., Is equal to or less than 0.25 L,;

2)

Has a duration sufficient to establish accurately the change in leakage rate between the Type A test and the supplemental test; and 3)

Requires that the rate at which gas is injected into the containment or.

bled from the containment during the supplemental test is between 0.75 L, and 1.25 L.

d.

Type B and C tests shall be conducted with gas at a pressure greater than or equal to P 38.57 psig, at intervals no greater than 24 months exceptfortestsI,nvolving:

1)

Air locks e.

The combined bypass leakage rate shall be determined to be less than or equal to 0.042 L, by applicable Type B and C tests at least once per 24 months except for penetrations which are not individ1 ally testable; penetrations not individually testable shall be determined to have no detectable leakage when tested with soap bubbles while the containment is pressurized to greater than or equal to P.,

38.57 psig, during each Type A test; f.

Air locks shall be tested. and demonstrated OPERABLE by the requirements of Specification 4.6.1.3; g.

Purge supply and exhaust isolation valves shall be demonstrated OPERABLE by the requirements of Specifications 4.6.3.2.c and 4.9.9.

h.

The provision; of Specification 4.0.2 are not applicable.

gLSTONE-UNIT 3 3/4 6-3 Amendment No. 77, 75. JPP, W

9 CONTAINMENT SYSTEMS CONTAINMENT AIR LOCKS LINITING CONDITION FOR OPERATION

3. 6.1. 's The containment air lock shall be OPEPABLE with:

a.

Both doors closed except when the air lock is beino used for normal transit entry and exit through the containment, then at least one air lock door shall be closed, and b.

An overall air lock leakage rate of less than or equal to 0.05 L, at P., 38.57 psig.

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

AC11QN:

a.

With one containment air lock door inoperable:

1.

Maintain at least the OPERABLE air lock door closed

• and either restore the inoperable air lock door to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or lock the OPERABLE air lock door closed, 2.

Operation may then continue until performance of the next required overall air lock leakage test provided that the OPERABLE air lock door is verified to be locked closed at least once per 31 days, 3.

Otherwise, be in at least HOT STANDBY 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 />, and 4.

Entry into an OPERATIONAL MODE is permitted while subject to these ACTION requirements, b.

With the containment air lock inoperable, except as the result of an inoperable air lock door, maintain at least one air lock door closed; restore the inoperable air lock to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or be in at least HOT STANDBY 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 />.

• Except during entry to repair an inoperable inner door, for a cumulative time not to exceed I hour per year.

MILL 5 TONE - UNIT 3 3/4 6-5 Amendment No. 57, 77, 154 eue

CONTAINMENT SYSTEMS SURVEILLANCE REQUIRENENTS 4.6.1.3 Each containment air lock shk11 be demonstrabd OPERABLE:

a.

1)

Within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> following each ;1osing, except when the air lock is being used for multiple entries, then at least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> by verifying no detectable seal leakage by pressure decay wh,n the volume between the door seals is pressurized to e

greater than or equal to P., 38.57 psig, for at least 15 minutes; l or 2)

Within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> following each clostnn'then a; least once l>er 72

, excest when the air lock is being used for multiple entries hours, by verifying that the seal le,akage is less than 0.0h L, as determined by 1)recision flow measurements when measured for at least 30 seconc s with the volume between the seals at a constant pressure of greater than or equal to P., 38.57 psig; l

or 3)

Within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> rollowing each closing, exce)t when the ai lock is bein hours, s used for multiple entries, then a" least once per 72 sy completing an overall air lock leakage test per 4.6.1.3.b.

b.

by conducting overall air lock leakage tests at a pressure arenter than or equal to P*, 38.57 psig, and verifying the overall air lock leakage rate is within its limit:

1)

At least once per 6 months,* and 2)

Prior to establishing CONTAINMENT INTEGRITY when maintenance has beer. performed on the air lock that could affect the air lock sealing capability.**

c.

At least once per 6 months by verifying that only one door in each air lock can be opened at a time.

• The provisions of Specification 4.0.2 are not applicable.

• • This represents an exemption to Appendix J, paragraph 111.D.2.(b)(ii), of 10 CFR Part 50.

JNL5 TONE - UNIT 3 3/4 6-6 Amendment No. M.154

3/4.6 CONTAlletENT SYSTEN5 BASES 3/4.6.1 PRIMARY CONTAINMENT 3/4.6.1.1 CONTAINMENT INTEGRITY Primary CONTAINNENT INTEGRITY ensures that the release of radioactive materials from the containment atmosphere will be restricted to those leakage paths and associated leak rates assumed in the safety analyses. This restric-tion, in conjunction with the leakage rate limitation, will limit the SITE BOUNDARY radiation doses to within the dose guideliras of 10 CFR Part 100 during accident conditions and the control room operators dose to within the guidtlines of GDC 19.

The opening of locked or scaled closed containment isolation valves on an interm'.ttent basis under administrative control includes the following considerations:

(1) stationing an operator, who is in constant communication with control room, at the valve controls, (2)d (3)l instructing this eperator to close these valves in an accident situation, an assuring that environmental conditions will not p"aclude access to close the va ves and that this action will prevent the release of radioactivity outside the containment.

3/4.6.1.2 CONTAINMENT LEAKAGE The limitations on containment leakage rates ensure that the total containment leakage volume will not exceed the value assumed in the safety analyses at the peak acciaent pressure, P,.

As an added conservatism, the measured overall integrated leakage rate is further limited to less than 0.75 L. l during performance of the periodic test to account for possible degradat M of the centainment leakage barriers between leakage tests.

The Limiting Condition for Operation defines the limitations on containment '

leakage rates for compliance with 10CFR50, Appendix J.

The leakage rates are verified by surveillance testing in accorcance with the requirements of Appendix J.

Although the LCO specifies the leakage rates at accident pressure, P., it is not feasible to perform a test at such an exact value for pressure.

Consequently, the surv::111ance testing is performed at a pressure greater than or equal to P, to account for test instrument uncertainties ar.d stabilization changes. This conservative test pressure ensures that the measured leakage rates are representative of those which would occur at accident pressure while meeting the intent of the LCO.

This test methodology is consistent with the guidance provided in ANS!/ANS 56.8 1981 for meeting the requirements set forth in Apoendix J.

The surveillance testing for measuring leakage rates are consistent with the requirements of Appendix J of 10 CFR Part 50. A partial exempt b n has been granted from the requireaents of 10CFR50, Appendix J.Section III.D.1(a). The exemption removes the requirement that ths third Type A test for each 10 year period be conducted when the plant is shut down for the 10 year plant inservice

-inspection (Reference License Amendment No. 111).

N NILL 5T0NE - UNIT 3 B3/4-6-1 Amendment No. JJ, JJ, JJJ,.154 ew

3/4.'8 CONTAINMENT SYSTEM 5 BASES 3/4.6.1.2 CONTAINMENTLEAKAGE(co??inued)

The enclosure butiding bypass leakagt paths are listed in Operating Procedure 3273, ' Technical Requirements Supplemantary Technical Specifica-tiens.'

The addition or deletion of the enclosure butiding bypass leakage paths shall be :nade in accordance with Section 50.59 of 10CFR50 and approved

[by the Plant Operation Review Committee.

~

3/4.6.1.3 CONTAINMENT AIR LOCKS Tha limitations on closure and leak rate for the containment air locks are required to meet the restrictions on CONTAINMENT INTEGRITY and containment leak rate.

Surveillance testing of the air lock seals provides assurance that the overall air lock leakage will not become excessive due to seal damage during the intervals between air lock leakage tests.

While the leakage rate limitation is specified at accident pressure, P., the actual surveillance testing is performed by applying a pressure greater than or equal to P,.

This higher pressure accounts for test instrument ut. certainties and test volume stabilization changes which occurs under actual test conditions.

This method of performing surveillance testing is consistent with the guidance provided in ANSI 56.8 1981 and ensures that the leakage rate measurec meets the intent of the LCO and Appendix J.

3/4.6.1.4 and 3/4.6.1.5 AIR PRESSVRE and AIR TEMPERATURE The limitations on containment pressure and average air temperature ensure that:

design negative (1) the containment structure is prevented from exceeding its pressure of 8 psia, and (2) the conttinment

>eak pressure does not exceed the design pressure of 60 psia during LOCA concitions.

Measure-ments shall be made at all listed locations, whether by fixed or portable instruments, prior to determining the average air temperature.

The limits on the )ressure and average air temperature are consistent with the assumptions of tie safety analysis.

The minimum total containment pressure of 10.6 psia is determined by summing the minimum permissible air partial pressure of 8.9 psia and the maximum expected vapor pressure of 1.7 psia maximum permissible containment initial temperature of 120'F)(occurring at the s

MILLSTONE - UNIT 3 B3/46-la Amendment No. 77, 77, 154 I