ML17059B229
| ML17059B229 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 08/13/1996 |
| From: | Jeffrey Mitchell NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML17059B230 | List: |
| References | |
| NUDOCS 9608160262 | |
| Download: ML17059B229 (40) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 IAGARA MOHAWK POWER CORPORATION DOCKET NO. 50-410 NIN MILE POINT NUCLEAR STATION UNIT 2 AMENDM NT TO FACILITY OPERATING LICENSE Amendment No.74 License No. NPF-69 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Niagara Mohawk Power Corporation (the licensee) dated February 7,
- 1996, as supplemented July 26,
- 1996, 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 1;
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 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.
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-69 is hereby amended to read as follows:
9608i60262 9608i3 PDR",,ADOCK,@05000@i 0,.
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(2)
Technical S ecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, both of which are attached
- hereto, as revised through Amendment No.
74 are hereby incorporated into this license.
Niagara Mohawk Power Corporation shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
Also, the license is amended by replacing paragraph 2.D.ii on page 6 of Facility Operating License NPF-69 with the following:
ii) Exemptions to certain requirements of Appendix J to 10 CFR Part 50 are described in Supplements 3, 4, and 5 to the SER.
These include (a)
(this item left intentionally blank);
(b) an exemption from the requirement of Option B of Appendix J, exempting main steam isolation valve measured leakage from the combined leakage rate limit of 0;6 La.
(Section 6.2 '
of'SER 5)*; (c) an exemption from Option B of Appendix J,
exempting the hydraulic control system for the reactor recirculation flow control valves from Type A and Type C leak testing (Section 6.2.6 of SSER 3); (d) an exemption from Option 8 of Appendix J,
exempting Type C testing on traversing incore probe system shear valves.
(Section 6.2.6, SSER 4) 4.
This license amendment is effective as of the date of its issuance to be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION Attachments:
1.
Page 6 of License NPF-69 2.
Changes to the Technical Specifications Date of Issuance-August 13, 1996 Jocelyn A. Mitchell, Acting Director Project Directorate I-1 Division of Reactor Projects - I/II
. Office of Nuclear Reactor Regulation
TTACHMENT 1
TO LICENSE AMENDMENT AMENDMENT NO. 74 TO FACILITY OPERATING LICENSE NO. NPF-69 DOCKET NO. 50-410 Revise License NPF-69 as follows:
Remove Pa e
Insert Pa e
\\
l
An exemption from the criticality alarm requirements of 10 CFR Part 70.24 was granted in the Special Nuclear Materials License No. SNM-1895 dated November 27, 1985.
This exemption is described in Section 9.1 of Supplement 4 to the SER.
This previously granted exemption is continued in this operating license.
Exemptions to certain requirements of Appendix J to 10 CFR Part 50 are described in Supplements 3, 4, and 5 to the SER.
These include (a) (this item left intentionally blank); (b) an exemption from the requirement of Option B of Appendix J, exempting main steam isolation valve measured leakage from the combined leakage rate limitof 0.6 La. (Section 6.2.6 of SSER 5) '; (c) an exemption from Option B of Appendix J, exempting the hydraulic control system for the reactor recirculation flow control valves from Type A.and Type C leak testing (Section 6.2.6 of SSER 3); (d) an exemption from Option B of Appendix J, exempting Type C testing on traversing incore probe system shear valves.
(Section 6.2.6, SSER 4) iii)
An exemption to Appendix A to 10 CFR Part 50 exempting the Control Rod Drive (CRD) hydraulic lines to the reactor recirculation pump seal purge equipment from General Design Criterion (GDC) 55. The CRD hydraulic lines to the reactor recirculation pump seal purge equipment use two simple check valves for the isolation outside containment (one inside).
(Section 6.2.4, SSER 3) iv)
A schedular exemption to GDC 2, Appendix A to 10 CFR Part 50, until the first refueling outage, to demonstrate the adequacy of the downcomer design under the plant faulted condition.
This exemption permits additional analysis and/or modifications, as necessary, to be completed by the end of the first refueling outage.
(Section 6.2.1.7.4, SSER 3) v)
A schedular exemption to GDC 50, Appendix A to 10 CFR Part 50 to allow Niagara Mohawk Power Corporation until start-up following the "mini-outage," which is to occur within 12 months of commencing power operation (entering Operational Condition 1), to install redundant fuses in circuits that use transformers for redundant penetration protection in accordance with their letter of August 29, 1986 (NMP2L 0860).
(Section 8.4.2, SSER 5)
The parenthetical notation following the discussion of each exemption denotes the section of the Safety Evaluation Report (SER) and/or its supplements wherein the safety evaluation of the exemption is discussed.
Amendment No. 7<
ATTACHMENT 2 TO LICENSE AMENDMENT AMENDMENT NO. 74 TO FACILITY OPERATING LICENSE NO.
NPF-69 DOCKET NO. 50-410 Revise Appendix A as follows:
Remove Pa e
3/4 6-1 3/4 6-2 3/4 6-3 3/4 6-4 3/4 6-5 3/4 6-6 3/4 6-7 3/4 6-9
'/4 6-10 3/4 6-45 3/4 6-46 B3/4 6-1 83/4 6-2 6-17a Insert Pa e
3/4 6-1 3/4 6-2 3/4 6-3 3/4 6-4 3/4 6-5 3/4 6-6 3/4 6-7 3/4 6-9 3/4 6-10 3/4 6-45*
3/4 6-46 B3/4 6-1 B3/4 6-2 6-17a 6-17b**
Overleaf page (for TS with two-side copies text not changed)
- New page
I
~ 3/4 6 CONTAINMEN YSTEMS 4.6.1 PRIMARY NTAINMENT PRIMARY NTAINMENTINTE RITY LIMITINGCONDITIONS FOR OPERATION 3.6
~ 1.1 PRIMARY CONTAINMENT INTEGRITY shall be maintained.
APPLICABILITY: OPERATIONAL CONDITIONS 1, 2*, and 3.
~AT~IN:
Without PRIMARY CONTAINMENT INTEGRITY, restore PRIMARY CONTAINMENT INTEGRITY 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 SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
RVEILLANCE RE UIREMENT 4.6.1.1 PRIMARY CONTAINMENT INTEGRITY shall be demonstrated:
a.
After each closing of each penetration subject to Type B testing, except the primary containment air locks, if opened following Type A or B test, by leak rate testing the seals in accordance with the 10 CFR 50 Appendix J Testing Program Plan.
At least once per 31 days by verifying that all primary containment 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 va(ves secured in position, except as provided in Specification 3.6.3.
d.
By verifying each primary containment air lock is in compliance with the requirements of Specification 3.6.1.3.
By verifying the suppression chamber is in compliance with the requirements of Specification 3.6.2.1.
See Special Test Exception 3.10.1 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 such verification need not be performed when the primary containment has not been de-inerted since the last verification or more often than once every 92 days.
NINE MILE POINT - UNIT 2 3/4 6-1 Amendment No. k$
74
NTAINMENT Y
PRIMAR NTAINMEN.
PRIMARY T INM T L
'KA LIMITIN DITI N F
PERATI N
3.6.1.2 Primary containment leakage rates shall be limited to:
a.
An overall integrated leakage rate of less than La, 1.1% by weight of the containment air every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at Pa, 39.75 psig.
b.
A combined leakage rate on a minimum pathway basis of less than 0.60 La for all penetrations and all Primary Containment Isolation Valves, except for main steam line isolation valves'and Primary Containment Isolation Valves which are hydrostatically. leak tested), subject to Type 8 and C tests when pressurized to Pa, 39.75 psig.
C.
d.
A combined leakage rate of less than or equal to 1 gpm times the total number of containment isolation valves in hydrostatically tested lines which penetrate the primary containment, when tested at 1.10 Pa, 43.73 psig.
Less than or equal to that specified in Table 3.6.1.2-1 through valves in lines that are
'otential bypass leakage pathways when tested at 40.0 psig.
Y ON T
lt i
i d
3.6.1.1.
~ATI NN:
With:
a.
The measured overall integrated primary containment leakage rate equaling or exceeding 1.0 La or Exemption to Appendix J of 10 CFR 50 NINE MILE POINT - UNIT 2 3/4'-2 Amendment No. 6~74
0
NTAINMENT Y PRIMARY TAIN EN PRIMARY LEAK LIMIT(N D T F
R PERATI 3.6.1.2 (Continued)
~T~I b.
'i The measured combined leakage rate on a minimum pathway basis for all penetrations and
),
all Primary Containment Isolation Valves, except for main steam line isolation valves'nd valves which are hydrostatically leak tested, subject to Type B and C tests equaling or exceeding 0.60 La, or C.
The measured combined leakage rate for all containment isolation valves in hydrostatically tested lines which penetrate the primary containment exceeding 1 gpm times the total number of such valves, or d.
The measured leakage rate through any valve that is part of a potential bypass leakage pathway exceeding the limit specified in Table 3.6.1.2-1 Restore:
80 The overall integrated leakage rate to less than 1.0 La, and b.
The combined leakage rate on a minimum pathway basis for all penetrations and all Primary Containment Isolation Valves, except for main steamline isolation valves'nd valves which are hydrostatically leak tested, subject to Type B and C tests to less than 0.60 La, and C.
The combined leakage rate for all containment isolation valves in hydrostatically tested lines which penetrate the primary containment to less than or equal to 1 gpm times the total number of such valves, and d.
The leakage rate to less than or equal to that specified in Table 3.6.1.2-1 for any valve that is part of a potential bypass leakage path.
Exemption to Appendix J to 10 CFR 50 NINE MILE POINT - UNIT 2 3/4'-3 Amendment No. B1 va74
~
~
NTAINMENT Y T PRIMARY ONTAINM T
PRIMARY CONTAINMENTLEAKAGE URVEILLAN E RE UIREMENTS 4.6.1.2.1 The primary containment leakage rates shall be demonstrated at test schedules and in conformance with the criteria specified in the 10 CFR 50 Appendix J Testing Program Plan as described in Section 6.8.4,f.
4.6.1.2.2 Main steam line isolation valves and the remainder of the valves specified in-Table 3.6.1.2-1 shall be leak tested in accordance with the 10 CFR 50 Appendix J Testing Program Plan as described in Section 6.8.4.f at a test pressure of at least 40 psig with air or nitrogen to demonstrate that each valve satisfies the leakage limits specified in Table 3.6.1.2-1.
4.6.1.2.3 Containment isolation valves in hydrostatically tested tines which penetrate the primary containment shall be leak tested in accordance with the 10 CFR 50 Appendix J Testing Program Plan as described in Section 6.8.4.f at a test pressure of at least 1.10 Pa, 43.73 psig.
4.6.1.2.4 The provisions of Specification 4.0.2 are not applicable to Surveillance Requirements 4.6.1.2.1, 4.6.1.2.2, and 4.6.1.2.3.
NINE MILE POINT - UNIT 2 3/4 6-4 Amendment No. 33, Ek, kk74
. 'ONTAINMENTSYS PRIMARY CONTAINMENT PRIMARY CONTAINMENTLEAKAGE RVEILLAN E RE UIREMENTS THIS PAGE LEFT INTENTIONALLY8LANK NINE MILE POINT - UNIT 2 3/4 6-6 Amendment No. 74
i TABLE 3.6.1.2-1 ALL WABLE LEAK RATE THROU H VALVE IN P
TENTIALBYPASS LEAKAGE PATHS LINE DE RIPTI N
VALVEMARK N TERMINATION
~Rllt PER VALVE I
LEAK RATE, ila 4 Main Steam Lines 2MSS*AOV6A, B, C, D 2MSS*AOV7A, B, C, D Turbine Bldg.
24.0 Main Steam Drain Line (Outboard) 2MSS*MOV208 Main Steam Drain Line (Inboard) 2MSS*MOV111, 112 Turbine Bldg.
1.875 Turbine Bldg.
0.625 4 Postaccident Sampling Lines 2CMS*SOV77A, B 2CMS*SOV74A, B 2CMS*SOV75A, B 2CMS*SOV76A, B Radwaste Tunnel 0.2344 Drywell Equipment Drain Line Drywell Equipment Vent Line Drywell Floor Drain Line Drywell Floor Vent Line RWCU Line Feedwater Line CPS Supply Line to Drywell
.CPS Supply Line to Drywell CPS Supply Line to Supp.
Chamber
'CPS Supply Line to Supp.
Chamber 2DER*MOV119 2DER*MOV120 2DER*MOV130 2DER*MOV131 2DFR*MOV120 2DFR*MOV121 2DFR*MOV139 2DFR*MOV140 2WCS*MOV102 2WCS*MOV112 2FWS*AOV23A 2FWS*V1 2A 2FWS*AOV23B 2FWS*V12B 2CPS*AOV104 2CPS*AOV106 2CPS*SOV1 20 2CPS*SOV122 2CPS*AOV105 2CPS*AOV107 2CPS*SOV1 1 9 2CPS*SOV121 Radwaste Tunnel Radwaste Tunnel Red waste Tunnel Red waste Tunnel 1.25 0.625 1.875 0.9375 Turbine Bldg.
2.5 Turbine Bldg.
12.0 Standby Gas 4.38 Trtmt. Area Standby Gas 0.625 Trtmt. Area Standby Gas 3.75'rtmt.
Area Standby Gas 0.625 Trtmt. Area NINE MILE POINT - UNIT 2 3/4 6-6 Amendment No. kk ~74
t TABLE 3.6.1.2-1 (Continu ALLOWABLELEAK RATES THROUGH VALVES IN POTENTIAL BYPASS LEAKAGE PATHS LINE DESCRIPTION
~...inst. Air to ADS Valve Accumulator Inst. Air to ADS Valve Accumulator Nz Purge to TIP Index Mechanism Inst. Airto SRV Accumulator Inst. Air to Drywell Inst. Air to Drywell Inst. Air to CPS Valve in Suppression Chamber Inst. Air to CPS Valve in Suppression Chamber VALVEMARK NO IAS*SOV164 IAS*V448 IAS*SOV165 IAS*V449 GSN*SOV1 66 GSN*V170 IAS*SOV166 IAS*SOV1 84 IAS*SOV1 67 IAS*SOV185 IAS*SOV168 IAS*SOV180 CPS*SOV132 CPS*V50 CPS*SOV133 CPS*VS1 Yard Area 0.9375 Yard Area Yard Area Yard Area Yard Area Yard Area Yard Area PER VALVE I
TERMINATION LEAK RATE, REGION SCFH Yard Area 0.9375 The combined leakage of these six penetrations shall not exceed 3.6 SCFH.
The leakage through each penetration shall be that of the valve with the highest rate in that penetration.
NINE MILE POINT - UNIT 2 3I4 6-7 Amendment No. 74
CONTAINMENTSY PRIMARY C NTAINMENT PRIMARY NTAINMENTAIR LOCKS RVEILLAN E RE IREMENTS 4.6.1.3 Each primary containment air lock shall be demonstrated OPERABLE:
By verifying seal leakage rate less than or equal to 5 scf per hour when the gap between the door seals is pressurized to greater'than or equal to 10 psig:
1
~
Within 7 days following each closing, except when the air lock is being used for multiple entries, then at least once per 7 days; and 2.
Prior to establishing PRIMARY CONTAINMENT INTEGRITY when the air lock has been used.
b.
By conducting an overall air lock leakage test at Pa, 39.75 psig and by verifying that the overall air lock leakage rate is within its limit at a test schedule in accordance with the 10 CFR 50 Appendix J Testing Program Plan, d.
'y verifying that only one door in each air lock can be opened at a time prior to performing SR 4.6.1,3.a. f The provisions of Specification 4.0.2 are not applicable, and the surveillance interval extensions are in accordance with the 10 CFR 50 Appendix J Testing Program Plan.
Except that the inner door need not be opened to verify interlock OPERABILITY when the primary containment is inerted, provided that the inner door interlock is tested within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> after the primary containment has been de-inerted.
NINE MILE POINT - UNIT 2 3/4 6-9 Amendment No. 74
~ C NTAINMENT Y
S PRIMARY NTAINMENT PRIMARY CONTAINMENTSTRUCTURAL INTEGRITY LIMITIN C
NDITI NS FOR OPERATI N
3.6.1.4 The structural integrity of the primary containment shall be maintained at a level consistent with the acceptance criteria in Specification 4.6.1.4.
~
ACTION:
With the structural integrity of the primary containment not conforming to the above requirements, restore the structural integrity to within the limits 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 SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
RVEILLANCE RE UIREMENTS 4.6.1.4.1 The structural integrity of the exposed accessible interior and exterior surfaces of the primary containment, including the liner plate and drywell to wetwell bypass paths, shall be determined by a visual inspection of those surfaces.
This inspection shall be performed to verify no apparent changes in appearance or other abnormal degradation at an inspection schedule in accordance with the 10 CFR SO Appendix J Testing Program Plan.
4.6.1.4.2 Any abnormal degradation of the containment structure detected duririg the above required inspections shall be reported to the Commission pursuant to Specification 6.9.2 within 30 days.
This report. shall include a description of the condition of the vessel and the annulus fill concrete, the inspection procedure, the tolerances on concrete cracking, and the corrective actions taken.
NINE MILE POINT - UNIT 2 3/4 6-10 Amendment No. 74
CONTAINMENT SYSTEMS SECONDARY CONTAINMENT STANDBY GAS TREATMENT SYSTEM SURVEILLANCE RE UIREMENTS
- 4. 6. 5. 3 (Continued) d.
At least once per 18 months by:
1.
Verifying that the pressure drop across the combined HEPA filters and charcoal adsorber banks is less than 5.5 inches Water Gauge while operating the filter train at a flow rate of 4000 cfm t lOX.
2.
Verifying that the filter train starts and isolation valves open on each of the following test signals:
a.
Manual initiation from the 'control
- room, and b.
Simulated automatic initiation signal.
3.
Verifying that the decay heat removal air inlet valves are closed and can be manually opened.
4.
Verifying that the heaters dissipate
- 20. 0 a 2. 0 kW when tested in accordance with ANSI N510-1980.
e.
After each complete or partial replacement of a HEPA filter bank by verifying that the HEPA filter bank satisfies the inplace penetration and bypass leakage testing acceptance criteria of less than 0.05K in accordance with ANSI N510-1980 while operating the system at a flow rate of 4000 cfm k lOX.
f.
After each complete or partial replacement of a charcoal adsorber bank by verifying that the charcoal adsorber bank satisfies the inplace penetra-tion and bypass leakage testing acceptance criteria of less than 0.05X in accordance with ANSI N510-1980 for a halogenated hydrocarbon refrigerant test gas while operating the system at a flow rate of 4000 cfm k 10X.
NINE MILE POINT - UNIT 2 3/4 6"45
'ONTAINMENT Y 4.6.6 PRIMARY NTAINMENTATM PHERE NTR L
DRYWELLAND UPPRESSI N CHAMBER HYDROGEN RE MBINER SY TEM LIMITING NDITI NS F R OPERATION 3.6.6.1 Two independent drywell and suppression chamber hydrogen recombiner systems shall be OPERABLE.
APPLICABILITY: OPERATIONAL CONDITIONS 1 and 2.
ACTION:
With one drywell and/or suppression chamber hydrogen recombiner system inoperable, restore the inoperable system to OPERABLE status within 30 days or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
SURVEILLANCE REQUIREMENTS 4.6.6.1 Each drywell and suppression chamber hydrogen recombiner system shall be demonstrated OPERABLE:
a.
At least once per 6 months by verifying during a recombiner system functional test that the minimum heater coil outlet gas temperature increases to greater than or equal to 1150 F within 90 minutes.
Maintain 1150 F or more for at least 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
At least once per 18 months by:
1.
Performing a CHANNEL CALIBRATIONof all recombiner'instrumentation and control circuits.
Verifying the integrity of all heater electrical circuits by performing a resistance to ground test within 30 minutes following the above required functional test.
The resistance to ground for any heater phase shall be greater than or equal to 1 million ohms.
By measuring the system leakage rate:
1.
As a part of the overall integrated leakage rate test required by Specification 3.6.1.2, or By measuring the leakage rate of the system outside of the containment isolation valves at Pa, 39.75 psig, on the schedule required by Specification 4.6.1.2.1, and including the measured leakage as a part of the leakage determined in accordance with Specification 4.6.1.2.1.
NINE MILE POINT - UNIT 2 3/4 6-46 Amendment No. 74
3 4.6 ONTAINME YSTEMS BA E
4.
PRIMARY NTAINMENT 4.
1 PRIMARY NTAINMENTINTE RITY PRIMARY CONTAINMENTINTEGRITY 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 accident analyses.
This restriction, in conjunction with the leakage rate limitation, will limit the control room and site boundary radiation doses to within the limits of General Design Criterion (GDC) 19 and 10 CFR 100 during accident conditions.
2 RIMA Y NTAINMENT EAK The limitations on primary containment leakage rates ensure that the total containment leakage volume will not exceed the value assumed in the accident ana'lyses at a pressure of 39.75 psig, Pa.
Updated analysis results in a maximum expected pressure of less than 39.75 psig. As an added conservatism, the measured overall integrated leakage rate is further limited to less than or equal to 0.75 La during performance of the periodic tests to account for possible degradation of the containment leakage barriers between leakage tests.
Operating experience with the main steam line isolation valves has indicated that degradation has occasionally occurred in the leak tightness of the valves; therefore, the special requirement for testing these valves.
The surveillance testing for measuring leakage rates is consistent with the requirements of Option B of Appendix J of 10 CFR 50 with the exception of an exemption granted for main steam isolation valve testing.
Leak testing of valves in potential bypass leakage pathways is performed at a test pressure of 40.00 psig rather than Pa, 39.75 psig, for consistency with the accident analysis.
The leakage rates specified for the main steam line isolation valves, the main steam drain line isolation valves, and the postaccident sampling system gas sample and return line block valves are used to quantify the maximum amount of primary containment atmosphere that could bypass secondary containment and leak directly to the environment after a design-basis loss-of-coolant accident.
These data are used to determine the radiological consequences of this accident and ensure that the resultant doses are within the limits of GDC 19 and 10 CFR 100.
3 4.6.1.
PRIMARY ONTAINMENTAIR LO K
The limitations on closure and leak rate for the primary containment air locks are required to meet the restrictions on PRIMARY CONTAINMENTINTEGRITY and the primary containment leakage rate given in Specifications 3.6.1.1 and 3.6.1.2.
The specification makes allowances for the fact that there may be long periods of time when the air locks will be in a closed and secured position during reactor operation.
Only one closed door in each air lock is required to maintain the integrity of the containment.
NINE MILE POINT - UNIT 2 B3/4 6-1 Amendment No. kki74
CONTAINMENTSY C
BA E
PRIMARY NTAINMENT 3 4.6.1.4 PRIMARY C NTAINMENTSTRUCTURAL INTEGRITY This limitation ensures that the structural integrity of the containment will be maintained comparable to the original design standards for the life of the unit. Structural integrity is required to ensure that the containment will withstand. the design pressure of 45 psig in the event of a loss-of-coolant accident (LOCA). A visual inspection at a frequency as required by the 10 CFR 50 Appendix J Testing Program Plan is sufficient to demonstrate this capability.
4.6.1.
DRYWELL AND PPRE ION HAMBER INTERNAL PRES RE The limitations on drywell and suppression chamber internal pressure ensure that the containment peak pressure of less than 39
~ 75 psig does not exceed the design pressure of 45.0 psig during LOCA conditions or that the external pressure differential does not exceed the design maximum external pressure differential of 4.7 psi. The limit of 14.2 to 15.45 psia for initial positive containment pressure will limit the total pressure to 39.75 psig, which is less than the design pressure and is consistent with the safety analysis.
4.6.1.6 DRYWELL AVERA E AIR TEMPERATURE The limitation on drywell average air temperature ensures that the containment peak air temperature does not exceed the design temperature of 340'F during steam line break conditions and is consistent with the safety analysis.
ln addition, the maximum drywell average air temperature is also the limiting initial condition used to determine the maximum negative differential pressure acting on the drywell and suppression chamber following inadvertent actuation of the containment sprays.
3/4.6.1.7 PRIMARY CONTAINMENT PURGE SYSTEM The 14-inch drywell and 12-inch suppression chamber supply and exhaust valves are limited to 135 hours0.00156 days <br />0.0375 hours <br />2.232143e-4 weeks <br />5.13675e-5 months <br /> of use per 365 days during purge or vent operations in OPERATIONAL CONDITIONS 1.
2, and 3 to meet the requirements of Branch Technical Position CSB 6-4 and Generic Letter 83-02 for valves greater than 8 inches in diameter.
The requirement to limit the opening of 2CPS'AOV105, 2CPS'AOV107, 2CPS "AOV109, and 2CPS'AOV110 to 70 degrees, and 2CPS'AOV111 to 60 degrees ensures these valves will close during a LOCA or steam line break accident, and therefore, the site boundary dose guidelines of 10 CFR 100 would not be exceeded in the event of an accident during purging or venting operations.
NINE MILE POINT - UNIT 2 B3/4 6-2 Amendment No. k(, kk,7'
"l
ADMINI TRATIVE R
L R
ED RE AND PR RAM PR RAM 6.8.4 (Continued) e.
Di IF I
il in Pr r m A diesel fuel oil testing program to implement required testing of both new fuel oil and stored fuel oil shall be established.
The program shalt include sampling and testing requirements, and acceptance criteria, all in accordance with applicable ASTM Standards.
The purpose of the program is to establish the following:
Acceptability of new fuel oil for use prior to addition to storage tanks by determining that the fuel oil has:
a.
an API gravity or an absolute specific gravity within limits, b.
a flash point and kinematic viscosity within limits, and c.
a clear and bright appearance; 2.
Other properties for ASTM fuel oil are within limits within 31 days following addition to storage tanks; and 3.
Total particulate concentration of the fuel oil is <10 mg/I when tested every 31 days in accordance with ASTM D-2276, Method A.
1 FR A
n ix T
in Pr r
Pl A program shall be established to implement the leakage rate testing of the containment as required by 10 CFR 50.54(o) and 10 CFR 50, Appendix J, Option 8 with the exemptions stated in Section 2.D(ii) of the Operating License.
This program shall be in accordance with the guidelines contained in Regulatory Guide 1.163, entitled, "Performance-Based
~ Containment Leak-Test Program," dated September 1995 with the following exceptions:
1.
Main steam isolation valves'easured leakage is excluded from the combined leakage rata of 0.6 La, and as-found testing is not required to be performed on the main steam isolation valves.
2.
Primary containment airlocks'oor seals are tested prior to re-establishing containment integrity when something has been done that would bring into question the validity of the previous airlock door seal test.
The peak calculated containment internal pressure (Pa) for the design basis loss of coolant accident is 39.75 psig.
The maximum allowable primary containment leakage rate (La) at Pa shall be 1.1 lo of primary containment air weight per day.
NINE MILE POINT - UNIT 2 6-17a Amendment NQ. 6s74
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ADMINI TRATIVE C R
6.8.4.f (Continued)
Leakage Rate acceptance criteria are:
Primary Containment leakage rate testing acceptance criterion is less than 1.0 La.
The combined leakage rate for Type B and C tests on a minimum pathway basis, except for main steam line isolation valves" and Primary Containment isolation valves which are hydrostatically tested, is less than 0.6 La.
During the first unit startup following testing in accordance with this program, the as-left leakage rate acceptance criteria are less than 0.6 La for the Type 8 and C tests on a maximum pathway basis, except for main steam line isolation valves'nd Primary Containment isolation valves which are hydrostatically tested, and less than or equal to 0.75 La for Type A tests; 2.
Air lock testing acceptance criteria are:
a.
Overall air lock leakage rate is less than or equal to 0.05 La when tested at greater than or equal to Pa, 3.
b.
For each door, leakage rate is less than or equal to 5 scfh when the gap between the door seals is pressurized to greater than or equal to 10 psig.
Hydrostatic testing acceptance criterion is a combined leakage rate of less than or equal to 1 gpm times the total number of containment isolation valves in hydrostatically tested lines which penetrate primary containment, when tested at 1.10 Pa, 43.73 psig.
The provisions of SR 4.0.2 do not apply to the test frequencies specified in the 10 CFR 50 Appendix J Testing Program Plan.
The provisions of SR 4.0.3 are applicable to the 10 CFR 50 Appendix J Testing Program Plan.
" Exemption to Appendix J to 10 CFR 50 NINE MILE POINT - UNIT 2 6-1 7b Amendment No. 74
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