ML17191B473
| ML17191B473 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 10/01/1999 |
| From: | Anthony Mendiola NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML17191B474 | List: |
| References | |
| NUDOCS 9910120314 | |
| Download: ML17191B473 (8) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 2055S-0001 COMMONWEAL TH EDISON COMPANY DOCKET NO. 50-237 DRESDEN NUCLEAR POWER STATION. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 175 License No. DPR-19
- 1.
The Nuclear Regulatory Commission (the Commission) has fourid that:
A.
The application for amendment by the Commonwealth Edison Company (the
- licensee) dated June 15, 1999, 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 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. DPR-19 is hereby amended to read as follows:
9910120314 991001 i
\\
PDR ADOCK 05000237
.P
. PDR i
I (2)
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.
175, 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 and shall be
- implemented within 30 days.
Attachment:
Changes to the Technical Specifications Date of Issuance: October 1, 1999 FOR THE NUCLEAR REGULA TORY COMMISSION
/~?c:.-c::.
~o~y J. Mendiola, Chief, Section 2
,~ectDirectorate Ill Division*of Licensing Project Management Office of Nuclear Reactor Regulation
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. ~1 COMMONWEAL TH EDISON COMPANY DOCKET NO. 50-249 DRESDEN NUCLEAR POWER STATION, UNIT 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 1 71 License No. DPR-25
- 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by the Commonwealth Edison Company (the licensee) dated June 15, 1999, 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;
- 8.
- 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 riot 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 3.8. of Facility Operating License No. DPR-25 is hereby amended to read as follows:
B.
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.* 171, 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 and shall be implemented within 30 days.
Attachment:
Changes to the Technical Specifications Date of Issuance: October 1, 1999 FOR THE NUCLEAR REGULATORY COMMISSION 0,,cd
~nthony J. Mendiola, Chief,.Section 2
' Project Directorate Ill Division of Licensing Project Management Office of Nuclear Reactor Regulation
.. r
ATIACHMENT TO LICENSE AMENDMENT NOS. 175 AND 171 FACILITY OPERATING LICENSE NOS. DPR-19 AND DPR-25
- DOCKET NOS. 50-237 AND 50-249 Revise the Appendix "A" Technical Specifications by replacing the pages identified below with the enclosed pages. The revised pages are identified by the amendment number and contain a vertical line in the margin indicating the area of change.
REMOVE 3/4.7-7 83/4.7-2 INSERT 3/4.7-7 *.
83/4.7-2 83/4.7-2a
CONTAINMENT SYSTEMS PCIVs 3/4.7.D 3*.7 - LIMITING CONDITIONS FOR OPERATION 4.7 - SURVEILLANCE REQUIREMENTS
- 2.
With one or more reactor instrumentation line excess flow check valves inoperable, operation may continue and the provisions of Specification 3.0.C are not applicable, provided that within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> either:
- a.
The inoperable valve is restored to OPERABLE status, or
- b.. The instrument line is isolated and the associated instrument is declared inoperable.
Otherwise, 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 />.
DRESDEN - UNITS 2 & 3 3/4.7-7
- a.
At least once per 31 days by verifying the continuity of the explosive charge.
- b.
At least once per 18 months by
- removing at least one explosive squib from an explosive valve such that each explosive squib will be tested at least once per 90 months, and initiating the removed explosive squib(s). The replacement charge for tne exploded squib(s) shall be
, from the same manufactured batch as the one fired or from another batch which has been certified by having at least one of that batch successfully fired. No squib shall remain in use beyond the expiration of its shelf-life or operating life, as applicable.
- 6.
In accordance with the methods and at the frequency specified by the Primary Containment Leakage Rate Testing Program, verify total maximum pathway leakage for all Main Steam Isolation Valves is~ 46-scfhwhen tested at P1 (25 psig).
Amendment Nos. 175 and 171
CONTAINMENT SYSTEMS B 3/4.7 BASES leakage tests). The acceptance criteria were established during initial air lock and primary containment.
OPERABILITY testing. The periodic testing requirements verify that air lock leakage does not exceed the allowed fraction of the overall primary containment leakage rate. The Frequency is required by the Primary Containment Leakage Rate Testing Program. The surveillance requirements have been annotated such that an inoperable air lock door does not invalidate the previous successful performance of the overall air lock leakage test. This is considered reasonable since either air lock door is capable of providing a fission product barrier in the event of a DBA.. Additional annotation is provided to require the results of air lock leakage tests being evaluated against the acceptance criteria applicable to the surveillance requirements. This ensures that the air lock leakage is properly accounted for in determining the combined Type B and Type C primary containment leakage.
3/4.7.D Primary Containment Isolation Valves The OPERABILITY of the primary 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. Containment isolation within the time limits specified tor those 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.
The containment is also penetrated by a large number of small diameter instrument lines which contact the primary coolant system: A program for periodic testing and examination of the flow check valves in these lines is performed by blowing down the instrument line during a vessel hydro and observing conditions which verify that the flow check valve is operable, e.g., a distinctive 'click' when the poppet valve seats, or an instrumentation high flow that quickly reduces to a slight trickle.
The main steam line isolation valves *are tested at lower pressures, per an approved exemption, but the
- ieakage rate is included in the Type B and C test totals. The surveillance testing tor measuring leakage rates is consistent with the requirements of Appendix J of 1 OCFR Part 50 with the exception of approved
. exemptions. (Ref: Exemption Request Approval, Mr. D. G. Eisenhut (NRG) to Mr. L. DelGeorge (CECo) dated June 25, 1982.)
'. The individual main steam isolation valve (MSIV) leakage limit has been replaced by the aggregate leakage limit of :$; 46 scth tor all MSIVs. The leakage will be determined tor the maximum pathway leakage in accordance with the Primary Containment Leakage Rate Testing Program. This is a very conservative total tor MSIV leakage because it takes the MSIV with the maximum leakage in each steam line and sums the leakage for each of those valves to determin*e the maximum pathway leakage.
DRESDEN - UNITS 2 & 3 B 3/4.7-2 Amendment Nos. 175 and 171
CONTAINMENT SYSTEMS B 3/4. 7 BASES 3/4.7.E Suppression Chamber - Drvwell Vacuum Breakers The function of the suppression chamber to drywell vacuum breakers is to relieve vacuum in the drywell.
- These internal vacuum breakers allow air and steam flow from the suppression chamber to the drywell when the drywell is at a negative pressure with respect to the suppression chamber. Each vacuum breaker is a self-actuating valve, similar to a check valve.
The safety analysis assumes that the internal vacuum breakers are closed initially and are fully open at a differential pressure of 0.5 psid. Additionally, three of these internal vacuum breakers DRESDEN - UNITS 2 & 3 B 3/4.7-2a Amendment Nos. 175 and p1