ML20059G237
| ML20059G237 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe (DPR-03-A-135, DPR-3-A-135) |
| Issue date: | 09/06/1990 |
| From: | Nerses V Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20059G227 | List: |
| References | |
| NUDOCS 9009120207 | |
| Download: ML20059G237 (5) | |
Text
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UNITED STATES n
NUCLE AR REGULATORY COMMISSION q
5 WASHINGTON, D. C. 20566 l
i YANKEE ATOMIC ELECTRIC COMPANY
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DOCKET N0.50-029 YANKEE NUCLEAR POWER STATION AMENDMENT TO FACILITY OPERATING LICENSE I
1 Amendment No.135
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License No.'DPR-3 1.
The Nuclear Regulatory Comission (the Commission or the NRC) has found that.
A.
The application for amendment filed by Yankee Atomic Electric Company (thelicensee)datedApril 19, 1990 and supplemented on June 7, 1990 i
complies with the standards and requirements of=the Atomic Energy Act of 1954, as amended (the Act),= and the Comnission's rLles and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the
. I provisions of the Act, and the rules and regulations of.the l
Comission-l C.
There is reasonable assurance: (i)'thattheactivitiesauthorizedby this amendment can be conducted without endangering the health.and safety of the public, and (ii) that such activities wili he conducted I
in compliance with the Commission's regulations set forth in 10 CFR Chapter I; 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 Specifica-1 tiens as indicated in the attachment to this license amendment, and-paragraph 2.C.(2) of Facility Operating Licenst No. DPR-3 is hereby amended to read as follows:
(2) Technical Specifications-L The Technical Specifications contained in Appendix A, as revised through Amendment No.135, are hereby incorporated in the license.
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i The licensee shall operate the facility in accordance with the 1
L
. Technical Specifiestions.
l 900912O207 900906 I
PDR ADOCK 05000029 b l
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e 2-3.
This license amendment is effective'as of its date of-issuance.
FOR THE NUCLEAR REGULATORY COMMISSION O
LALA o Victor Nerses.' Acting Director.
Project Directorate I-3 Division of Reactor Projects 1/11 Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
September 6',' 1990 t
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I ATTACHMENT TO LICENSE AMENDMEl'T N0.135 FACILITY OPERATING LICENSE NO. DDR-3 DOCKET N0.50-029 1
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Replace the following lages of the Appendix A Technical Specifications with the attached pages. Tae revised pages are identified by Amendment number and co nain vertical lines indicating the area of change.
Remove Insert 3/4 5-4 3/4 5-4 B 3/4 5-2 3/4 5-2 P
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suavriitAuct aanutarw xrt 4.5.2' Each ECCS safety injection subsystem, the recirculation subsystem, and the long-term hot leg injection subsystem shall be demonstrated OPERABLE:
4.
By testing each of the following pumps pursuant to Specification a.
4.0.5 1.
High Pressure Safety Injection Pumps 2.
Low Pressure Safety' Injection Pumps b.
At least once per 31 days by:
1.
Verifying that the.following valves are in the indicated positions with power to the valve operators removed by opening at least two breakers in series:
Valve Number Valve Function Valve Position
- a. CH-MOV-52?.
- a. Charging Header /LPSI
- a. Closed Isolation-i I
YANKEE-ROWE 3/4 5-4 Amendment No. 35, 52, 92, !!9,13g,135 7
o EMERCENCY CORE COOLING SYSTEMS nms 1
ECCS SUBSYSTEMS (Continuedl With the Main Coolant System temperature and pressure below 330'F and 1,000 psig, respectively, one OPERABLE ECCS safety injection subsystem, with the OPERABLE recirculation subsystem and the OPERABLE long-term hit leg injection subsystem, is acceptable without single failure consideration on the basis of the stable reactivity condition of the reactor, the decreased probability of a LOCA, and the limited core cooling requirements because of the negligible energy stored in the primary coolant under these conditions.
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.
I Complete system tests cannot be performed when the reactor is operating because of their inter-relation with operating systems. The method of assuring operability of these systems is a combination of complete system J
tests performed during refueling shutdowns and, inservice testing of active system components (pumps and valves) during reactor operation. The test interval is based on the judgment that msre frequent testing would not significantly increase reliability.
Some subsystems' power operated valves fail to meet single failure criteria and removal of power to these valves is required.
In order to eliminate potential for reactor vessel low temperature overpressurization by the inadvertent operation of ECCS pumps, the pump circuit breakers are opened and locked in the racked-out position or removed from the breaker cubicles.
Also selected SIS isolation valves are positioned to remove the possibility of an overpressurization event during that portion of MCS heatup and cooldown when an inadvertent injection could result in an overpressure event.
3/4.5.4 SAFETY INJECTION TANK The OPERABILITY cf the Safety Injection Tank (SIT) as part of the ECCS ensures that a sufficient supply of borated water is available for injection by the ECCS in the event of a LOCA. The limits on SIT minimum volume and boron concentration ensure that 1) sufficient water is available within containment to permit recirculation cooling flow to the core, and 2) the reactor will remain suberitical in the cold condition following mixing of the SIT and the Main Coolant System water volumes with all control rods inserted except for the most reactive control assembly. These assumptions are consistent with the l
LOCA analyses, which is based on allowing a minimum of 77,000 gallons to be injected by the safety injection subsystems before the recirculation is manually established. LOCA analyses show that an injection of 77,000 gallons is sufficient to limit core temperatures and containment pressure for the full spectrum of pipe ruptures.
This leaves up to 40,000 gallons in the SIT as reserve.
The boron concentration of 2,200 ppm is the highest value assumed in any accident analysis. The SIT water temperature of 120'F to 130*F ensures i
that the reactor vessel is not subjected to conditions that could exceed the NDT provisions of the ASME Code after a severe transient.
YANKEE-ROWE B 3/4 5-2 Amendment No. 51, jf. 91.135
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