ML20217Q745
| ML20217Q745 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 08/28/1997 |
| From: | Mckee P NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20217Q747 | List: |
| References | |
| NUDOCS 9709030344 | |
| Download: ML20217Q745 (6) | |
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t UNITED STATES l
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NUCLEAR REGULATORY COMMISSICN o
e WASHINGTON, D.C. 20e#4001 s.,...../
NORTHEAST NUCLEAR ENERGY COMPANY. ET AL.
DOCKET NO. 50-423 MILLSTONE NUCLEAR POWER STATION. UNIT NO. 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.1147 License No. NPF-49 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Northeast Nuclear Energy Company, et al. (the licensee) dated May 5,1997, 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 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 o
requirements Lve been satisfied.
9709030344 970828 PDR ADOCK 05000423 P
.<. 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)llows:of-Facility Operating License No. NPF-49 is hereby amended to read as fo (2).
Technical Soecifications The Technical Specifications contained in ' Appendix A, as revised through Amendment No. 147, 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 O
Phillip F'.
McKee Deputy Director for Licensing Special Projects Office Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: August 28, 1997
ATTACHMENT TO LICENSE AMENDMENT NO. 147 FACILITY OPERATING LICENSE NO. NPF-49 DOCKET NO. 50-423 Replace the following sages of the Appendix A, Technical Specifications, with the attached pa Tie revised pages are identified by amendment number and containverticakes. lines indicating the areas of change.
I Remove Insert 3/4 5-4 3/4 5-4 B 3/4 5-2 B 3/4 5-2 l
B 3/4 5-2a*
1--
- overflow page - no change O
1 ENERRENCY C0RE COOLING SYSTEMS I
SURVEILLANCE REQUIREMENTS 4.5.2 Each ECCS subsystem shall be demonstrated OPERABLE:
a.
At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by verifying that the following valves are in the indicated positions with power to the valve operators removed:
Valve Number Valve Function Valve Position 3SIH*MV8806 RWST Supply to SI Pumps OPEN 3SIH*MV8802A SI Pump A to Hot Leg Injection CLOSED 3SIH*MV8802B SI Pump 8 to Hot Leg Injection CLOSED 3SIH*MV8835 SI Cold Leg Master Isolation OPEN 3SIH*MV8813 SI Pump Master Miniflow OPEN
! solation 3SIL*MV8840 RHR to Hot leg Injection CLOSED 3SIL*MV8809A RHR Pump A to Cold Leg OPEN Injection 3SIL*MVB8098 RHR Pump B to Cold Leg OPEN Injection b.
At least once per 31 days by:
1)
Verifying that the ECCS piping, except for the operating centrifugal charging pump (s) and associated piping, the RSS pump, the RSS heat exchanger and associated piping, is full of water, and 2)
Verifying that each valve (manual, power-operated, or automatic) in the flow path that is not locked, sealed, or otherwise secured in position, is in its correct position, By a visual inspection which verifies that no loose debris (rags, c.
trash, clothing, etc.) is present in the containment which could be transported to the containment sump and cause restriction of the pump suctions during LOCA conditions. This visual inspection shall be performed:
1)
For all accessible areas of the containment prior to establish-ing CONTAINMENT INTEGRITY, and 2)
At least once daily of the areas affected (during each day) within containment by containment entry and during the final entry when CONTAINMENT INTEGRITY is established, d.
At least once each REFUELING INTERVAL by:
1)
Verifying _ automatic interlock action of the RHR System from the
-Reactor Coolant System by ensuring that with a simulated or actual Reactor Coolant System pressure signal greater than or
-equal to 390 psia the interlocks prevent the valves from being opened.
MIgLSTONE-UNIT 3 3/4 5-4 Amendment No. pp, 77, 199, J1#, 147 l
EMERGENCY CORE COOLING SYSTEMS l
BASES ECCSSUBSYSTEMS(Continued)
The limitation for a maximum of one centrifugal charging pump and one safety injection pump to be OPERABLE and the Surveillance Requirement to verify all charging pumps and safety injection pumps except the required
_}
OPERABLE charging pump to be inoparable below 350'F provides assurance S
that a mass addition pressure transient can be relieved by the operation of a single PORV.
The Surveillance Requirements provided to ensure OPERABILITY of each component ensures that at a minimum, the assumptions used in the safety analyses are met and that subsystem OPERABILITY is maintained.
Surveillance Requirements for throttle valve position stops and flow balance testing srovide assurance that proper ECCS flows will be maintained in the event of a
.0CA Maintenance of proper flow resistance and pressure drop in the piping system to each injection point is necessary to:
(1) prevent total pump flow from exceeding runout conditions when the system is in its minimum resistance configuration, (2) provide the proper flow s)1it between injection points in accordance with the assumptions used in t1e ECCS-LOCA analyses, and (3) provide an acce.) table level of total ECCS flow to all injection points equal to or above t.1at assumed in the ECCS-LOCA analyses.
m Surveillance Requirement 4.5.2.b.1 requires verifying that the ECCS piping is full of water exce)t for the operating centrifugal charging pump (s) and associated piping, and tie RSS pump, the RSS heat exchanger and associated RSS piping. The ECCS pumps are normally in a standby, nonoperating mode, with the exception of the o)erating centrifugal charging pump (s). As such, the ECCS flow path piping 1as the potential to develop voids and pockets of entrained gases. Maintaining the piping from the ECCS pumps to the RCS full of water ensures that the system will perform properly when required to inject into the RCS. This Surveillance Requirement is met by venting ECCS pump casings and the accessible discharge piping high points except for:
(1) the RSS pump, RSS heat exchanger ar.d associated RSS piping that is not maintained filled with water during plant cperation is excluded from the Surveillance Requirement, (2) the operating centrifugal charging pump (s) and associated piping is also excluded as an operating pump is self venting and cannot develop voids and pockets of entrained gases, and (3) the nonoperating centrifugal charging pum)s do not have casing vent connections and the pump manufacturer indicates t1at venting the suction pipe will assure that the pump casing does not contain voids and pockets of entrained gases. The venting of the nonoperating centrifugal charging pumps is accomplished by venting with the suction line test connection.
Surveillance Requirement 4.5.2.C.2 requires that the visual inspection of the containment be performed at least once daily if the containment has been entered that day and when the final containment entry is made. This will reduce the number of unnecessary inspections and also reduce personnel exposure.
MILLSTONE - UNIT 3 8 3/4 5-2 Amendment No. Jpp,147 0613
E!tERFHCY CORE C00 LING SYSTDis BASES 3/4.5.4 REFUELING WATER STORAGE TANK
.The OPERABILITY of the refueling water storage tank (RWST as part of the ECCSensuresthatasufficientsupplyofboratedwaterisavaila)bleforinjec.
tion by the ECCS in the event of a LOCA. The limits on RWST minimum volume and boron concentration ensure thats containmenttopermitrecirculation(1)sufficientwaterisavailablewithin o
cooling flow to the core, and reactor will remain suberitical-in the cold condition following mix (2) theing of the RWST and the RCS water volumes with all control rods inserted except for the most reactive control assembly. These assumptions are consistent with the LOCA analyses.
The contained water volume limit includes an allowance for water not usable because of tank discharge line location or other physical characteristics.
The limits on contained water volume and boron concentration of the RWST also ensure a pH value of between 7.0 and 7.5 for the solution recirculated within containment after a LOCA.
This pH band minimizes the effect of chloride and caustic stress corrosion on mechanical systems and components.
The maximum / minimum solution temperatures for the PWST in MODES 1, 2, 3 and 4 are based on analysis assumptions.
MILL 5 TONE - UNIT 3 B 3/4 5-ta Amendment No.147 l
0613
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