ML20083D309
| ML20083D309 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 09/19/1991 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Northeast Nuclear Energy Co (NNECO) |
| Shared Package | |
| ML20083D311 | List: |
| References | |
| NPF-49-A-063 NUDOCS 9109300168 | |
| Download: ML20083D309 (9) | |
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DOCLET NO. 50 423 t'1 L L 5TO!tE !;UC_L E Ap, P,0yE k,,5,T A,TJ ON,,,UhJ T,,fl0..,,3 APEfWHEllT TO FACILITY CFEPATittG LICEllSE Amendo:ent !!o. 63 License No. NPF-49 1.
The Nuclear Pegulatory Commission (the Commission) has found that:
-The app (lication for amendment by f ortheast fluclear Energy Company, A.
et al.
the licensee) dated June 6, 1991, 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 Connission; C.
There is reasonable assurance (i) that the activities authorized by this anendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will ae 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 anendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
9109300160 910919 PDR ADOCK 05000423 P
. 7.
Accordingly, the liccnse is aretc'ed by changes to the Technical Specifications es indicated in the attachroent to this license ar endo.ent, and paragraph P.C.(2) of facility Cperating License !!o. t4PF 49 is hercby atended to reed as follows:
(I)
.I f!'.h.i.c,a,1,,5 p e.t i,f,i p a t i o n s F
The Technical Specificatic'ns contained in Appendix A, as r evised through An endtrent f40. 63
, and the Erivironniental Protection Plan contair'ed in Appendix 0, both of which are attached hereto are hercLy incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications and the Environnental Drotection Plan.
3.
This license amendnent is effective as of the date of its issuance, to be inpier;ented within 30 days of issuance.
FOR THE ttUCLEAR PEGULATORY C0f'FISS10t1 Joh
. Stolz, Director Pro ett Directorate 1-4 1 ision of Reactor Projects - 1/11 Of fice of fluclear Peactor Pegulation
Attachment:
Changes to the Technical Specifications Date of Issuance: September 19, 1991
ATTACHMENT TO LICENSE AMENDriENT NO. 63 FACILITY OPERATING LICENSE NO. NpF 49 DOCKET NO. 50-4?3 l
Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised pages are identified by amendnent number and contain vertical lines iudicating the areas of change.
Remove Insert ix ix 3/4 6-36 3/4 6-36 3/4 6-36a 3/4 6-36a B 3/4 6-3 B 3/4 6-3 B 3/4 6-3a B 3/4 6-3b l
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INDEX LlHITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION Eh.E Air Temperature...................................
3/4 6 9 Containment Structural Integrity..................
3/4 6 10 Containment Ventilation System....................
3/4 6-11 3/4.6.2 DEPRESSURilATION AND COOLING SYSTEMS Containment Quench Spray System....................
3/4 6 12 Recirculation Spray System.........................
3/4 6 13 Spray Additive System..............................
3/4 6 14 3/4.6.3 CONTAINMENT ISOLATION VALVES.......................
3/4 6-15 3/4.6.4 COMBUSilBLE GAS CONTROL Hydrogen Monitors..................................
3/4 6 35 Electric Hydrogen Recombiners......................
3/4 6-36 3/4.6.5 SUBATMOSPHERIC PRESSURE CONTROL SYSTEM Steam Jet Air Ejector..............................
3/4 6-37
,4.6.6 SECONDARY CONTAINMENT Supplementary Leak Collection and Release Systent...
3/4 6-3B Enclo?ure Building Integrity.......................
3/4 6 40 Enclosure Building Structural Integrity............
3/4 6-41 3/4.7 PLANT SYSTEMS 3/4.7.1 TURBINE CYCLE j
Safety Valves...........................................
3/4 7-1 TABLE 3.7-1 MAXIMUM ALLOWABLE POWER RANGE NEUTRON FLUX HIGH SETPOINT WITH IN0PERABLE STEAM LINE SAFETY VALVES DURING FOUR LOOP 0PERATION.........................
3/4 7-2 TABLE 3.7-2 MAXIMUM ALLOWABLE POWER RANGE NEUTRON FLUX HIGH SETPOINT WITH IN0PERABLE STEAM LINE SAFETY VALVES THREE LOOP OPERAT10N..............................
3/4 7-2 MILLSTONE - UNIT 3 ix Amendment No. E3 63 0043
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4 TONTAINMENT SYSTEMS
((ECTRIC HYOR0 GEN RECOMBINERS LIMITING CONDITION FOR OPERATION 3.6.4.2 Two independent Hydrogen Recombiner Systems shall be OPERABLE.
APPLICABillTY: MODES 1 and 2.
ACIlQN:
With one Hydrogen Recombiner System inoperable, restore the inoperable system to OPERABLE status within 30 days 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 />.
SURVEILLANCE RE0VIREHENTS 4.6.4.2 Each Hydrogen Recombiner System shall be demonstrated OPERABLE:
a.
At least once per 6 months by verifying during a Hydrogen Recombiner System functional test that the minimum reaction chamber gas temperature increases to greater than or equal to 700*F within 90 minutes and is maintained for at least 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and that the purge blower operates for 15 minutes.
b.
At least once per 18 months by:
1)
Performing a CHANNEL CAllBRATION of all recombiner instrumentation and control circuits, 2)
Verifying through a visual examination that there is no evidence of abnormal conditions within the recombiner enclosure (i.e., loose wiring or structural connections, deposits of foreign materials, etc.),
3)
Verifying the integrity of all heater electrical circuits by performing a resistance to ground test following the above required functional test.
The resistance to ground for any heater phase shall be greater than 10,000 ohms, and 4)
Verifying during a recombiner system functional test using containment atmospheric air at an acceptable flow rate as determined in Section 4.6.4.2.b.5 that the gas temperature increases to greater than or equal to 1100'F within 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> and is maintained for at least 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
5)
Verifying during a recombiner system functional test using containment atmospheric air that the blower would be capable of delivering at least 41.52 scfm at containment conditions of 12.47 psia and 130'f.
MILLSTONE - UNIT 3 3/4 6-36 Amendment No. 47,63 0045 l
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]RSTONE-UNIT 3 3/4 6-36a Amendment No. #, S 63
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CONTAINHENT SYSTEMS BASES 3/4.6.3 CONTAINMENT IS0(ATION VALVES The OPERABILITY of the containment isolation valves ensures that the containment atmosphere will be isolated from the outside environment in the event of a release of radioactive material to the containment atmosphere or pressurization of the containment and is consistent with the requirements of General Design Criteria 54 through 57 of Appendix A to 10 CFR Part 50.
Containment isolation within the time limits specified for these isolation valves designed to close automatically ensures that the release of radioactive material to the environment will be consistent with the assumptions used in the analyses for a LOCA.
FSAR Table 6.2-65 lists all containment isolation valves.
The addition of deletion of any containment isolation valve shall be made in accordance with Section 50.59 of 10CFR50 and approved by the Plant Operation Review Committee.
3/4.6.4 COMBUSTIBLE GAS CONTROL The OPERABILITY of the equipment and systems reqeired for the detection 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.
Either recombiner unit or the Mechanical Vacuum Pumps are capable of controlling the expected hydrogen generation associated with: (1) zirconium-water reactions (2) radiolytic decorposition of water, and (3) corrosion of metals within containment.
These Hydrogen Control Systems are consistent with the recommendations of Regulatory Guide 1.7, " Control of Combustible Gas Concentrations in Containment Following a LOCA," March 1971.
The Post-LOCA performance of the hydrogen recombiner blowers is based on a series of equations supplied by the blower manufactuer.
These equations are also the basis of the acceptance criteria used in the surveillance procedure.
The required performance was based on starting containment conditions before the LOCA of 10.59 psia (total pressure), 120'F and 100% relative humidiy.
The surveillance procedure shall use the following methods to verify acceptable blower flow rate:
1.
Definitions and constants CFM = cubic feet per minute RPM - revolutions per minute B1ower RPM = 3550 Blower ft3/ revolution =,028 ft3 Standard CFM = gas volume converted to conditions of 68'F and 14.7 psia.
HILLSTONE - UNIT 3 B 3/4 6-3 Amendment No. 4,63 0046
CONTAINHEHT SYSTEMS BASES 2.
Measure and record the following information:
Pcontainment--Average of 3LMS*P934, 935, 936, and 937 (psia)
Pout--From 3HCS-Pila cr B (psia)
Tc--Conta'snment temperatur'2 (*F)
Pin--Measure with a new inlet 9auge or calculate from Equation 3a below (psia) scfm measured--See Procedure / Form 3613A.3-1 AP --From Table 2 (psi) f A--As found Slip Constant Accuracy--Instrument accuracy range from Table 1.
3.
Calculate as found slip constant (A) a.
Pin - Pcontainment - APf scfm Accuracy -.I 14. 7. Tc + 469 '
3550 -
measured 0.02S
- 0.95
[ Nn 528 A=
,, Pin
- 14.7' N. ' 14.7. Tc + JL6Q )' 5 Eggi. 14.7 '
, "in 528 4.
Calculate expected postaccident flow rate us:..J A calculated in Step 3.
a.
Slip RPM
= A * (4.937)5
- 1.218 b.
Actual Inlet CFM ACFM =.028 (3550 - Slip RPM) c.
Standard CFM scfm - ACFM 0.725 d.
Portaccident scfm Minimum - scfm
- 0.9S e.
Acceptance Flow Rate Postaccident scfm minimum 2 41.52 scfm.
Mli.LSTONE - UNIT 3 B 3/4 6-3a Amendment No.,25,63 0046
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CONTAINMENT' SYSTEMS BASES-Table 1 Accuracy Range (Ref. 2) scfm (measured)
Accuracy Rance 40 to 50 5.8 scfm 50 to 80 4.7 scfm Table 2 Inlet Piping Loss (Ref.1) scfm Measured AP7 (psi)
(Unadiusted) 30
.21 40
.31 50
.52 60
.73 70
.98 80 1.28
References:
1.
Calculation 90 RPS-722GM, " Flow Acceptance Criteria for 3HCS*RBNR 1A/B Blowers 3HCS*C'A/B."
2.
Calculation PA 90-L0E-0132GE, " Hydrogen Recombiner Flow Error Analysis."
The acceptanct flow rate is the required flow rate at the worst case containment conai. ions 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after the LOCA. The analysis assumes the recombiners are started no later than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after the accident.
The 18-month surveillance shall verify the gas temperature and blower flow rate concurrently.
3/4.6.5 SUBATMOSPHERIC PRESSURE CONTROL SYSTEM 3/4.6.5.1 STEAM JET AIR EJECTOR
.The closure of the isolation valves in the' suction of the steam jet air ejector ensures that:
(1) the containment internal pressure may be maintained
-within its operation limits by the mechanical vacuum. pumps, and (2) the
. containment atmosphere is isolated from the outside environment in the evcnt of a LOCA. These valves are required to be closed for containment isolation.
MILLSTONE - UNIT 3 8 3/4 6-3b Amendment No. 25,63 0046.
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