ML20210A564

Amend 86 to License DPR-3,revising Tech Spec Surveillance Requirements for Containment Isolation Sys

ML20210A564
Person / Time
Site:	Yankee Rowe
Issue date:	11/08/1985
From:	Zwolinski J Office of Nuclear Reactor Regulation
To:
Shared Package
ML20210A535	List: ML20210A529 ML20210A564 ML20210A600
References
NUDOCS 8511150062
Download: ML20210A564 (23)

Text

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UNITED STATES 8 o NUCLEAR REGULATORY COMMISSION 5 ;y WASHINGTON, D. C. 20555

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YANKEE ATOMIC ELECTRIC COMPANY YANKEE NUCLEAR POVER STATION DOCKET NO. 50-29 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 86 License No. DPR-3

1. The Nuclear Regulatory Comission (the Commission) has found that:

A. The application for amendment by Yankee Atomic Electric Company (thelicensee)datedJuly 19, 1983, as modified April 17, 1984 and August 16, 1984, and as supplemented April 5,1985, 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 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 public; and (ii) that such activities will be conducted in compliance with the Comission's regulations; D. The issuance of this amendment will not be inimical to the comon 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 2.C.(2) of Facility Operating License No. DPR-3 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No.86 , 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.

FOR THE NUCLEAR REGULATORY COMMISSION

u. s s Joh A. Zwolinski, Chief Oper ting Reactors Branch #5 Division of Licensing

Attachment:

Changes to the Technical Specifications Date'of Issuance: November 8,1985 p

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ATTACHMENT TO LICENSE AMENDMENT N0. 86 FACILITY OPERATING LICENSE NO. DPR-3 DOCKET NO. 50-29 Revise Appendix A Technica! Specifications by removing the pages identified below and inserting the enclosed pages. The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of change. Overleaf pages (*) have been provided to maintain document completeness.

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REMOVE 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 6-4 3/4 6-4 3/4 6-5*

3/4 6-6 3/4 6-6 3/4 6-7*

,, 3/4 6-8 3/4 6-8 3/4 6-9 3/4 6-9 3/4 6-10*

3/4 6-11 3/4 6-11 3/4 6-12 3/4 6-12 3/4 6-13 3/4 6-13 3/4 6-14 3/4 6-14 3/4 6-14a 3/4 6-14a 3/4 6-15 3/4 6-15

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3/4 6-16 3/4 6-16*

B3/4 6-1 B3/4 6-1 B3/4 6-2 B3/4 6-2 B3/4 6-3 B3/4 6-3 J

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l 3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT CONTAINMENT INTEGRITY LIMITING CONDITION FOR OPERATION 3.6.I.I Primary CONTAINMENT INTEGRITY shall be maintained. ~

APPLICABILITY: MODES I, 2, 3 and 4 ACTION:

Without primary CONTAINMENT INTEGRITY, restore CONTAINMENT INTEGRITY within one 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 />.

i SURVEILLANCE REQUIREMENTS 4.6.1.1 Primary CONTAINMENT INTEGRITY shall be demonstrated:

,;_ a. At least once per 31 days by verifying that:

1. All penetrations not capable of being closed by OPERABLE containment automatic isolation valves and required to be closed during accident conditions are closed by valves, blind flanges, or deactivated automatic valves secured in their positions, except as provided in Table 3.6-1 of Specification 3.6.2 and

2. All equipment hatches are closed and sealed.

b. By calculating and plotting the containment air mass as determined by the containment continuous leak monitoring system at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

I

c. By verifying at least once per 3 months that all penetration l test, vent and drain connections and instrumentation ports

phoviding a direct path to the containment are isolated with i

' minimum of one cap, plug, closed valve, instrument or appropriate seal.

d. Any threaded pipe cap or threaded plug used to provide CONTAINMENT INTEGRITY will be torque tested on installation.

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l YANKEE RDWE 3/4 6-1 Amendment No.df,86 1

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CC%iAINMEhT SYSTEMS CONTAINY.ENT LEAPAGE LIMITING CONDITION FOR OPERATION 3.6.1.2 Containment leakage rates shall be limited to:

a. An overall integrated leakage rate of:

1. sL,0.20percentbyweightofthecontainm)ntair-per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at P,, 31.6 psig, or

2. sL 0.10 t ,

percent 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 a reduced pressure of Pg , 16 psig.

b. A combined leakage rate of less than or equal to 0.60 L, for all penetrations and valves subject to Type B and C tests as identified in Table 3.6-1 when presurized to P,.

APPLICABILITY: MODES 1, 2, 3 and 4.

., . ACTION: -

With either (a) the measured overall integrated containment leakage rate exceeding 0.75 L, or 0.75 Lt , as applicable, or (b) with the measured l combined leakage rate for all penetrations and values subject to Types B and C tests exceeding 0.60 L ,, restore the overall integrated leakage i rate of less than or equal to 0.75 L, or less than or eqoal to 0.75 L g l as applicable, and the combined rate for all penetrations subject to Type B and C tests to less than or equal to 0.60 L, prior to increasing the Main Coolant System temperature above 200'F.

SURVEILLANCE REQUIREMENTS 4

4.6.1.2 The containment leakage rates shall be demonstrated at the following.t'est schedule and shall be determined in conformance with criteria 4ecified in Appendix J of 10 CFR 50. using the methods and provisions of ANSI N45.4-(1972):

a. Three Type A tests (Overall Integrated Containment Leakage Rate) shall be conducted at 40110 month intervals during shutdown at either P,,

31.6 psig, or at P g,16 psig. during each 10 year service period. The third test of each set shall be conducted during the shutdown for the 10 year plant in-service inspection.

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YANKEE-ROWE 3/4 6-2 Amendment No. H ,86

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< CC*ilSS':E',i SYSTEMS SURVEILLANCE REQUIREMENTS (continued)

b. If any periodic Type A test fails to meet either .75 L, or .75 L g, 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 either 0.75'L, or 0.75 Lga Type A test shall be performed at least. every 18 l months until two consecutive Type A tests meet either 0.75 L, or 0.75 Lg at which time the above test schedule may be resumed.

c. The accuracy of each Type A test shall be verified by a supplemental test which requires the metered mass of gas injected into the containment or bled from the containment

. for the supplemental test to be equivalent to between 50 and 100% of the allowable 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> mass loss. The accept-ability is demonstrated if the mass change, as measured by the Type A instrumentation, agrees with the mass change as metered by the flow meter to within 25% of the allowable 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> mass loss.

- ; d. Type B and C tests shall be conducted with gas at P,, 31.6 -

psig, at intervals no greater than 24 months except for tests involving the air lock and the electrical penetrations.

, e. The air lock shall be tested and demonstrated OPERABLE per Specification 4.6.1.3.

f. The equipment and emergency hatch seals and seating surfaces shall be inspected before each hatch closure.

g. All test leakage rates shall be calculated using observed data converted to absolute values. Error analyses shall be per-formed to select a balanced integrated leakage measurement system.

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! h. Every four years 100% of all electrical penetrations (approxi-

,mately 25% per year) shall be locally leak tested subject to

,the following conditions:

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1. During testing of the electrical penetrations, any penetration

! which fails the leak test shall be included in the subsequent annual tests until two acceptable cons ~ecutive leak tests have been demonstrated, and

2. Those penetrations in Item 1 above shall be additional to those selected for testing during the subsequent annual test periods, i

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YANKEE-ROWE 3/4 6-3 Amendment No. 86 l

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CONTAINMENT SYSTEM CONTAINMENT AIR LOCK LIMITING CONDITION FOR OPERATION 3.6.1.3 The containment air lock shall be OPERABLE with:

a. Bothdoorsclosedexceptwhentheairlockisbeikyused'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 s 0.05 L, at P,, 31.6 psig.

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

With the air lock inoperable, restore the 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 />.

SURVEILLANCE REQUIREMENTS 4.6.1.3 The containment air . lock shall be demonstrated OPERABLE:

a. Within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> following each opening, 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 />, or within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> prior to entering a mode where containment integrity is required, by verifying a pressure drop of less than 0.2 psi when the air lock is pressurized to greater than or equal to Pa (31.6 psig) for at least 15 minutes. I

b. At least once per six months or prior to establishing CONTAINMENT INTEGRITY when maintenance has been performed on the air lock that -

could affect air lock sealing capability by conductin a:r lock leakage test at not less than Pa (31.6 psig)gand an overall verifying the overall air lock leakage rate is within its limit.

c. ,

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

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. YANKEE-ROWE 3/4 6-4 Amendment No. H.86

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W CONTAINMENT SYSTEMS .

INTERNAL PRESSURE . -

LIMITING CONDITION FOR OPERATION .

3.6.1.4 Primary containment internal pressure shall not exceed 3.0 psig.

APPLICABILITY: MODES 1, 2, 3 and 4.

ACTION:

With the containment internal pressure in excess of the limits above.

- restore the internal pressure to within the limits within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 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 />.

SURVEILLANCE REQUIREMENTS 4.6.1.4 The primary containment internal pressure shall be determined to l be within the limits at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

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YANKEE-ROWE 3/4 6-5

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'CONTA1N#.ENT SYSTEMS '

AIR TEMPERATURE LIMhTINGCONDITIONFOROPERATION 3.6.1.5 Primary containment average air temperature shall mot exceed 120*F.

APPLICABILITY: Modes 1, 2, 3 and 4. ~

ACTION:

With the containment average air temperature greater than 120*F, reduce the average air temperature to within the limit within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-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 />.

SURVEILLANCE REQUIREMENTS 4.6.1.5 The primary containment average air temperature shall be the weighted average of the temperature of at least fourteen of the following I twenty locations and sFril be determined at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. '

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Location -

a. Each main coolant loop - 4

b. Charging floor - I

c. Equipment hatch - 1

d. Top of Vapor Container - 1

e. Top of biological shield - 4

f. Broadway - 6

g. Pressurizer compartment - I

h. Brass drain box - 2 YANKEE-ROWE 3/4 6-6 Amendment No. 86

C

__0NTAINMENT SYSTEMS ,,,

C0f!TAINMENT VESSEL STRUCTURAL INTEGRITY ,

, LIMITING CONDITION FOR OPERATION _

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3.6.1.6 The structural integrity of the containment vessel shall be maintained at a level consistent with the acceptance criteria in Specification 4.6.1.6.

APPLICABILITY: MODES 1, 2. 3 and 4.

ACTION:

With the structural integrity of the containment vessel not conforming to the above requirements, restore the structural integrity to within the limits prior to increasing the Main Coolant System temperature above

'. l 200'F.

SURVEILLANCE REQUIREMENTS 4.6.1.6 The structural ~ integrity of the containment vessel shall be detenmined during the shutdown for each Type A containment leakage rate test (reference Specification 4.6.1.2) by a visual inspection of the accessible interior and exterior surfaces of the vessel and verifying no apparent changes in appearance of the surfaces or other abnormal degfadation.

An initial report of any abnormal degradation of the containment vessel detected during the above required inspections shall be made within 10 days after detection and the detailed report shall be submitted to the Commission pursuant,to Specification 6.9.1 within 90 days after completion of the surteillance requirements of this specification.

1 3/4 6-7 Arendment No. 58 TA:::".EE-RO*iE pg3 $N p .

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t.0'. : A; *,v. 'il 5% I EMS CONTINUOUS LEAK M3NITORING SYSTEM LIMITING CONDITION FOR OPERATION 3.6.1.7 The continuous leak monitoring system shall be OPERABLE within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> following establishment of CONTAINMENT INTEGRITY with:

a. Containment internal pressure greater than or equal to 0.75 psig,

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b. At least fourteen containment temperature detectors, l

c. At least.one containment pressure detector, and

d. Two relative humidity detectors and/or dew probes.

APPLICABILITY: Modes 1, 2, 3 and 4 ACTION:

With the continuous leak monitoring system inoperable, restore the system to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 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 />. SURVEILLANCE REQUIREMENTS 4.6.1.7 The continuous leak monitoring system shall be demonstrated OPERABLE by:

a. Verifying containment internal pressure te be greater than or equal to 0.75 psig at least once per 12 hours.

b. Calibrating the temperature channels, the pressure channels, the dew point channels or the relative humidity channels at least once per 18 months.

YANKEE-ROWE 3/4 6-8 Amendment No. H 86

CONTAINMENT SYSTEMS O 3/4.6.2 CONTAINMENT ISOLATION VALVES LIMITING CONDITION FOR OPERATION 3.6.2 The containment isolation valves specified in Table 3.6-1 shall be OPERABLE with isolation times as shown in Table 3.6-1. APPLICABILITY: Modes 1, 2, 3 and 4. -- ACTION: With one or more of the. isolation valve (s) specified in Table 3.6-1 inoperable either: .

a. Restore the inoperable valve (s) to OPERABLE status within 4 hours, or

b. Isolate each affected penetration within 4 hours by use of at least one deactivated automatic valve secured in the isolation position, or

c. Isolate each affected penetration within 4 hours by use of at least one closed manual valve or blind flange; or -

d. Be in at least HOT STANDBY within the next 6 hours and in COLD SHUTDOWN within the following 30 hours.

SURVEILLANCE REQUIRMENTS 4.6.2.1 The isolation valves specified in Table 3.6-1 shall be demonstrated OPERABLE:

a. At least once per 92 days by cycling each OPERABLE power operated or automatic valve testable during plant operation l

through at least one complete cycle of full travel. l b. Immediately prior to returning the valve to service after

                                       .m,aintenance, repair or replacement work is performed on the

• valve or its associated actuator, control or power circuit by performance of the cycling test, above, and verification of isolation time.

I YANKEE-RDWE 3/4 6-9 Amendment No.df 86 l

CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) 4.6.2.2 Each isolation valve specified in Table 3.6-1 shall jue demon-strated OPERABLE during the COLD SHUTDOWN or REFUELING MODE at least-once per 18 months by:

a. Verifying that on a containment isolation test signal, each automatic isolation valve actuates to its isolation position,

b. Cycling each power operated or automatic valve through at -l 1 east one canplete cycle of full travel and measuring the isolation time, and

c. Cycling each manual valve not locked, sealed or otherwise l secured in the closed position through at least one complete

. cycle of full travel. l YANKEE-ROWE 3/4 6-10 Amendment No. 49 MAY 3 0 57C v v' , - - - - --- - .

TABLE 3.6-1 CONTAINMENT 8ARRIERS TESTABLE DURING ISOLATION PLANT OPERATION TIME VALVE NUMBER FUNCTION (Yes or No) (Seconds) A.1 AUTOMATIC ISOLATION VALVES (Subject to Type C Testing) -

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VD-TV-202 Hain Coolant Drain Yes 30 VD-TV-203 Main Coolant Vent Yes 30 VD-TV-204 Valve Stem Leakoff Yes 30 SA-TV-206 Main Coolant Sample Yes 30 SA-TV-207 Neutron Shield Tank Sample . Yes 30 VD-TV-209 Containment Drain Yes 30

     .                  SW-TV-408      Containment Cooling Water Return         Yes                  30 SW-TV-412      Contatiiment Cooling Water Inlet         Yes                  30 HC-TV-409      Containment Heating Condensate Return    Yes                  30 HC-TV-413      Containment Heating Steam Supply         Yes                  30 PR-TV-214      Safety Discharge Header                  No                   30 CH-LCV-222    Main teolant Bleed                        Yes                  30 A.2 AUTOMATIC ISOLATION VALVES (Not Subject to Type C Testing)
 .               B.1 MANUAL VALVES (Subject to Type C Testing)

CS-V-601 Shield Tank Cavity Fill NA NA CA-V-746(3) Containment Air Charge NA NA HV-V-5 Containment H Vent System NA NA 2 HV-V-6(8) Containment H Vent System NA NA 2 [ HV-V-34(8) Containment H Vent System NA NA 2 CA-V-688 Containment Service Air Supply NA NA CA-V-834 Containment H Vent System Air Supply NA NA 2 CS-CV-216 Fuel Chute Dewatering Pump Discharge No NA VD-V-1103 0) Containment Sample NA NA VD-V-1108(10) Containment Sample NA NA CA-V-1275(8) H Recombiner Inlet Tap NA NA 2 CA-V-1276(8) H Recombiner Inlet Tap NA NA 2 l CA-V-1277(3) Containment Air Charge NA NA i l l l YANKEE ROWE 3/4 6-11 Amendment No.[,86

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TABLE 3.6-1 (continued) CONTAINMENT BARRIERS _ TESTABLE DURING ISOLATION PLANT OPERATION TIME VALVE NUMBER FUNCTION (Yes or No) (Seconds) VD-V-752(4) Neutron Shield Tank-Outer Test NA - NA VD-V-754 I4)

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Neutron Shield Tank-Inner Test' NA NA HC-V-602 Air Purge Bypass NA NA CA-V-755(6) VCPH Pressure Relief NA NA PU-V-651 Containment Sump to Charging NA NA VD-V-917 LPST S.V. Discharge Header NA NA

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P.2 MANUAL VALVES (Not Subject to Type C Testing) C. CHECK VALVES (Not Subject to Type C Testing) SI-V-14 Safety Injec' tion (HP) NA NA CS-V-621 Safety Injection (LP) NA NA _ . _ CH-V-611 MC Feed to Loop #4 NA NA

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D.1 REMOTE MANUAL VALVES (Subjec.t to Type C Testing) CC-TV-205(5) Component Cooling Return No NA CC-TV-208(5) Component Cooling Inlet No NA HV-50V-39 Hydrogen Monitoring Yes NA HV-50V-42 Hydrogen Monitoring Yes NA D.2 REMOTE MANUAL VALVES (Not Subject to Type C Testing) SC-MOV-551/ Shutdown Cooling In No NA 553 (1,2) SC-MOV-552/ Shutdown Cooling Dut No NA 554 (1,2) CH-MOV-522 0) MC Feed-to-Loop Fill Header No NA SI-MOV-516 ECCS Recirculation No NA SI-MOV-517 'ECCS Recirculation No NA YANKEE RDWE 3/4 6-12 Amendment No.69, 77,86

                        .                            TABLE 3.6-1               (continued)

CONTAINMENT BARRIERS TESTABLE DURING ISOLATION PLANT OPERATION TIME VALVE NUMBER FUNCTION (Yes or No)- (Seconds) f E.1 BARRIERS (Subject to Type B Testing) - Demineralized Water Supply (Blank Flange) NA NA Cavity Purification (Blank Flange) NA NA L.P. Vent Header (Blank Flange) NA NA Personnel Airlock NA NA Electrical Penetrations NA NA Fuel Chute (Blank Flange)(9) NA NA Air Purge Inlet (Blank Flange) NA NA Air Purge Outlet (Blank Flange) NA NA LPST Safety Valve Discharge Header 5 Blank NA NA Flanges NA NA E.2 BARRIERS (Not Subject to Type B Testing)

   -                18" Bolted Manway                                                            NA            NA Containment Leg Expansion Joints                                             NA            NA Fuel Chute Expansion Joints ( )                                              NA            NA Equipment Hatch                                                              NA            NA Containment Top Manhole Cover                                                NA            NA Containment Bottom Manhole Cover                                             NA            NA Pressurizer Heise Gauge Line                                                 NA            NA Containment Pressure Sensing Lines (two)                                     NA            NA F. SAFETY VALVES (Subject to Type C Testing)

SV-215 LPST Safety Valve II) NA NA SV-223 Valve Stem Leakoff Safety Valve NA NA SV-227 CCST Safety Valve NA NA 9 YANKEE R0WE 3/4 6-13 Amendment No[,86

TABLE 3.6-1 (continued) CONTAINMENT BARRIERS TESTABLE DURING ISOLATION PLANT OPERATION TIME VALVE NUMBER FUNCTION (Yes or No) (Seconds) G.1 SECONDARYAUTOMATICISOLATION(NotSubjecttoAppendixJ)(IN TV-411 Atmospheric Steam Dump Yes ' 30 TV-406' Main Steam Drain to Condenser Yes 30 TV-401A No. 1 SG Blowdown Yes 30 TV-401B No. 2 SG Blowdown Yes 30 TV-401C No. 3 SG Blowdown Yes 30 TV-401D No. 4 SG Blowdown Yes 30 NRV-405A Main Steam Non-Return Valve No 5 NRV-405B Main Steam Non-Return Valve No 5 NRV-405C Main Steam Non-Return Valve No 5 NRV-405D Main Steam Non-Return Valve No 5 G.2 SECONDARY MANUAL ISOLATION (Nr.,t subject to Appendix J) (11, 12) MS-V-627 Main Steam Bypass NA NA _. . MS-V-628 Main Steam Bypass NA NA MS-V-629 Main Steam Bypass NA NA MS-V-630 Main Steam Bypass NA NA SI-V-701 SI to Alternate SG Feed NA NA VD-V-1157 SSS to Alternate SG Feed NA NA AS-V-719 Emergency Feedwater Pump Steam Supply NA NA AS-V-720 Steam Drain NA NA BF-V-815 Manual Flow Control Bypass NA NA BF-V-816 Manual Flow Control Bypass NA NA BF-V-817 Manual Flow Control Bypass NA NA BF-V-818 Manual Flow Control Bypass NA NA CF-V-606 Chemical Feed NA NA CF-V-607 Chemical Feed NA NA CF-V-608 Chemical Feed NA NA CF-V-609 .

• Chemical Feed NA NA YANKEE ROWE 3/4 6-14 Amendment No. H .86

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TABLE 3.6-1 (continued) CONTAINMENT BARRIERS TESTABLE DURING ISOLATION PLANT OPERATION TIME VALVE NUMBER FUNCTION (Yes or No) (Seconds) G.3 SECONDARY REMOTE MANUAL ISOLATION (Not Subject to - Appendix J) (11, 12) _ MS-MOV-659 Emergency Atmospheric Steam Dump No NA MS-MOV-670 Emergency Atmospheric Steam Dump No NA MS-MOV-681 Emergency Atmospheric Steam Dump No NA MS-MOV-692 Emergency Atmospheric Steam Dump No NA EBF-MOV-557 Alternate SG Feed No NA BF-CV-1000 Feedwater Regulator No NA BF-CV-1100 Feedwater Regulator No NA BF-CV-1200 Feedwater Regulator No NA BF-CV-1300 Feedwater Regulator No NA BF-CV-1000A Regulating Flow Control Bypass No NA BF-CV-1100A Regulating Flow Control Bypass No NA _ _ .BF-CV-1200A Regulating Flow Control Bypass No NA BF-CV-1300A Regulating Flow Control Bypass No NA G.4 SECONDARY SAFETY VALVES (Not Subject to Appendix J)(11) SV-409A Main Steam Safety Valve NA NA SV-409B Main Steam Safety Valve NA NA SV-409C Main Steam Safety Valve NA NA SV-409D Main Steam Safety Valve NA NA SV-409E Main Steam Safety Valve NA NA Main Steam Safety Valve SV-409F NA NA SV-409G Main Steam Safety Valve NA NA SV-409H Main Steam Safety Valve NA NA SV-409I Main Steam Safety Valve NA NA SV-409J Main Steam Safety Valve NA NA SV-409K Main Steam Safety Valve NA NA SV-409L Main Steam Safety Valve NA NA I .. l l YANKEE ROWE 3/4 6-14a Amendment No.69, 77,86

o o TABLE 3.6-1 (Continued) TABLE NOTATION (1) T.S. 4.6.1.1.a.1 not applicable while in Modes 1 or 2, due to ALARA considerations.

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(2) Valves may be open under administrative contrcl while in Mode 4. (3) Valves may be open under administrative control while in Modes 1, 2, 3, or 4 for contaihment air charge. ' (4) Valves may be open under administrative control while in Modes 1, 2, 3, or 4 for neutron shield tank leakage test. (5) Normally open and closed by administrative controls. (6) CA-V-755 may be unlocked when personnel are in the Vapor Container. Valve may be open while in Modes 1, 2, 3, or 4 for depressurization of the V.C. personnel hatch during containment access or for testing. (7) CH-MOV-522 may be energized under administrative control. . (8) Valves may be open under administrative control while in Modes 1, 2, 3, or 4 for surveillance testing. (9) T.S. 4.6.1.1.a.1 not applicable while in Modes 1, 2, 3, 4, due to ALARA considerations. (10) Containment sample valves (VD-V-1107 and VD-V-1108) and their test taps (VD-V-902 and VD-V-909) may be opened under administrative control in order to sample containment air. (11) The ACTION statements of T.S. 3.6.2 and 3.0.3 do not apply. t (12) Secondary isolation valves may be open under administrative controls. 3/4'6-15 Amendment No.86 YANKEE-ROWE t

CONTAINMENT SYSTEMS 3/4.6.3 COM USTIBLE GAS CONTROL 1 HYDR 0 GEN ANALYZER i LIMITING CONDITION FOR OPERATION  ! l 3.6.3.1 The containment hydrogen analyzer shall be OPERABLE. l APPLICABILITY: MODES 1 and 2. ACTION: With the hydrogen analyzer inoperable restore the analyzer to OPERABLE status within 7 days or be in at least HOT STANDBY within the next 6 hours. M&w SURVEILLANCE REQUIREMENTS 4.6.3.1 The hydrogen' analyzer shall be demonstrated OPERABLE at least once per 92 days by performing a CHANNEL CALIBRATION using sample gases containing a nominal:

a. Zero voliane percent hydrogen. balance nitrogen, and Five volume percent hydrogen, balance nitrogen.

~ b. e e T

                                                              ,          YANKEE-ROWE                                                                                      3/4 6-16
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l

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

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3. 4.6 CZ AW'ENT SYSTEMS BASES 3/4.6.1 FRIMARY CONTAINMENT 3/4.6.1.1 CONTAINMENT INTEGRITY I

Primary CONTAINMENT INTEGRITY ensures that the release of radioactive materials from the containment atmosphere will be restricted to those l 1eakage paths and associated leak vates assumed in the accjdent analyses. This restriction, in conjunction with the leakage rate limitation, will limit the site boudary radiation deses to within the limits of 10 CFR 100 during accident conditions. Containment integrity is not required with Main Coolant System tempera-ture less than 200*F or pressure less than 300 psig because no steam will be generated in the unlikely event of a Main Coolant System rupture and hence, no driving force to release fission products from the con-tainment will exist. 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 accident analyses at the peak accident pressure, P,. As an added . conservatism, the measured overall integrated leakage rate is further~

    - ~

limited to less than or equal to 0.75 L, or 0.75 Lg, as applicable, during performance of the periodic test to account for possible de-gradation of the containment leakage barriers between leakage tests. l The surveillance testing for measuring leakage rates are' consistent with the requirements of Appendix "J" of 10 CFR 50 except for the exemption granted by letter dated September 2,1982 which waived the requirement for local leak testing of equipment and emergency hatch seals providing the containment continuous leak monitoring system is OPERABLE. The same letter also provided special surveillance schedule for testing containment electrical penetrations. 3/4.6.1.3 CONTAINMENT AIR LOCK The limitations on closure and leak rate for the containment air lock are require'd to meet the restrictions on CONTAINMENT INTEGRITY and containment leak rate. The intermediate tests of the containment air lock is in conformance with the requirements of 10 CFR 50 Appendix "J". YANKEE-ROWE B 3/4 6-1 Amendment No. 86 e ..  % ee up

• U/'. . Ad."'d. i SY 5; EMS BASES 3/4.6.1.4 INTERNAL PRESSURE The limitations on containment internal pressure ensure that the containment peak pressure does not exceed the design pressure of 34.5 psig during LOCA conditions.

The maximum peak pressure expected to be obtained from a LOCA event is 31.6 psig. The limit of 3.0 psig for initial positive containment pressure will limit the total pressure to 31.6 psig which is less than the design pressure and is consistent with the accident analyses. 3/4.6.1.5 AIR TEMPERATURE The limitations on containment average air temperature ensure that the overall containment average air temperature does not exceed the initial tem-perature condition assumed in the accident analaysis for a LOCA. 3/4.6.1.6 CONTAINMENT VESSEL STRUCTURAL INTEGRITY This limitation ensures that the structural integrity of the contain-ment will be maintained comparable to the original design standards for the life of the facility. Structural integrity is required to ensure that the

                                   ~' ~       containment will withstand the maximum pressure of 31.6 psig in the e(ent of a LOCA. A visual inspection in conjunction with Type A leakage tests is sufficient to demonstrate this capability.

3/4.6.1.7 CONTINUOUS LEAK MONITORING SYSTEM The OPERABILITY of the conti,nuous leak monitoring system provides some assurance that the containment equipment hatch seal, emergency hatch seal, containment leg expansion joints, fuel chute expansion joints and electrical penetrations are not leaking excessively between Type A leak tests. 3/4.6.2 CONTAINMENT ISOLATION VALVES The OPERABILITY of the containment isolation valves ensures that the containment atmosphere will be isolated from the outside environment in the event of pressurization of the containment. Containment isolation within the time limits. specified ensures that the release of radioactive material to the environmedt will be consistent with the assumptions used in the analyses for a LOCA. YANKEE-RDWE B 3/4 6-2 Amendment No. (9, 86 l t

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CC'. TAI'NENT SYST EMS BASES 3/4.6.3 COMBUSTIBLE GAS CONTROL , The OPERABILITY of the equipeent and systems required for the detec-tion and control of hydrogen gas ensures that this equipment will be available to maintain the hydrogen concentration within containment below its flammable limit during post-LOCA conditions. The purge system is capable of controlling the expected hydrogen generation associated with I (zirconium-water reactions,

2) radiolytic decomposition of water and 3) corrosion of metals within con '

tainment. The hydrogen recirculating system is provided to ensure adequate mixing of the containment atmosphere following a LOCA. This mixing action will prevent localized accumulations of hydrogen from exceeding the flammable limit. f YANKEE-ROWE B 3/4 6-3 Amendment No. 86

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