ML19254F109
| ML19254F109 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 10/16/1979 |
| From: | Ziemann D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19254F110 | List: |
| References | |
| TASK-05-06, TASK-5-6, TASK-RR NUDOCS 7911070045 | |
| Download: ML19254F109 (9) | |
Text
.
- p e "cauq'o, UNITED STATES
'i NUCLEAR REGULATORY COMMISSION E
WASHINGTCN, 0. C. 20656 o
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JERSEY CENTRAL POWER & LIGHT CrNPANY DOCKET NO. 50-219 OYSTER CREEK NUCLEAR GENERATING STATION, UNIT NO.1 MENDMENT TO PROVISIONAL OPERATING LICENSE Amendment No. ^2 License No. DPR-16 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Jersey Central Power & Light Cunpany (the licensee) dated October 3,1979, 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 confonnity 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 Conriission's regulations:
D.
The issuance of this amendment w 11 not be inimical to the common defense and security or to the heslth and safety of the nublic: and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements nave been satisfied.
1290 130 7911 070 O I 6 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachent to this license amendment and paragraph 3.B of Provisional Operating License No.
DPR-16 is hereby amended to read as follows:
B.
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 42, 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.
FOR THE NUCLEAR REGULATORY CCNMISSION o,_ i ?
Dennis L. Ziema Chief Operating Reactors Branch #2 Division of Operating Reactors AttacMent:
Changes to the Technical Specifications Date of Issuance: October 16, 1979 1290
!31
ATTACENENT TO LICENSE AMENDMENT NO. 42 PROVISIONAL OPERATING LICENSE NO. DPR--16 DOCKET NO. 50-219 Revise Appendix A Technical Specifications by renoving the pages identified below and inserting the enclosed pages. The revised pages are identified by the captioned amendment number and contain vertical lines indicating the areas of change.
PAGES
- 3. 3 -1 3.3-2 3.3 -2a 3. 3 -3
- 3.3-6
- 3. 3 -7
- There were no changes made to this page. The Technical Specification provisions have merely been repositioned.
1290 132
3.3-1 3.3 REACTOR COOLANT Applicability:
Applies to the operating status of the reactor coolant system.
Obj ective:
To assure the structure integrity of the reactor coolant system.
Specification:
A.
Pressure Temperature Relationships (i) Hydrostatic Leakage Tests - the minimum reactor ve sel temperature for hydrostatic leakage tests at a given pressure shall be in excess of that indicated by Curve A of Figure 3.3.1.
(ii) Heatup and Cooldown Operations: Reactor non-critical-the minimum reactor vessel temperature for heatup and cooldown operations at a given pressure when the reactor is not critical shall be in excess of that indicated by Curve B of Figure 3.3.1.
(iii) Power operations--The minimum reactor vessel temperature for power operations at a given pressure shall be in excess of that indicated by Curve C of Figure 3.3.1.
(iv) Appropriate new pressure temperature limits must be approved as part of this Technical Specification when the reactor system has reached ten effective full power years of reactor operation.
B.
Reactor Vessel Closure Head Boltdown The reactor vessel closure head studs may be elongated by.020" (1/3 design preload) with no restrictions on reactor vessel temperature as long as the reactor vessel is at atmospheric pressure.
Full tensioning of the studs is not permitted unless the temperature of the reactor vessel flange and closure head flange is in excess of 100*".
2.
Thermal Transients 1.
The average rate of reactor coolant temperature change during normal heatup and cooldown shall not exceed 100 F in any cne hour period.
2.
The pump in an idle recirculation loop shall not be started unless the temperature of the coolant within the idle recirculation loop is within 50 F of the reactor coolant temperature.
1290 133 Amendment No. 42
3,3-2 D.
Reactor Coolant System Leakage Reactor coolant leakage into the primary containment from unidentified sources shall not exceed 5 gpm.
T.n addition, the total leakage in the containment, identified and unidentified, shall not exceed 25 gpm.
If these conditions cannot be met, the reactor will be placed in the cold shutdown condition.
E.
Reactor Coolant Quality 1.
The reactor coolant quality shall not exceed the following limits during power operation with steaming rates to the turbine-condenser of less than 100,000 pounds per hour.
conductivity 2 u =ho/cm chloride ion 0.1 ppm 2.
The reactor coolant quality shall not exceed the following limits during power operation with steaming rates to the turbine-condenser of at least 100,000 pounds per hour.
conductivity 10 mho/cm chloride ion 1.0 ppm 3.
If Specification 3.3.E.1 and 3.3.E.2 cannot be met, the reactor shall be placed in the cold shutdown condition.
F.
Recirculation Loon 'perability 1.
The reactor shall not be operated with one or more recirculation loops out of service except as specified in Specification 3.3.F.2.
2.
Reactor operation with one idle recirculation loop is permitted provided that the idle loop is not isolated f rom the reactor vessel.
3.
If Specifications 3.3.F.1 and 3.3.F.2 are not met the reactor shall be placed in the cold shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
The reactor coolant system ( } is a primary barrier against the Bases:
release of fission products to the environs.
In order to provide assurance that this barrier is maintained at a high degree of integrity, restrictions have been placed on the operating conditions to which it can be subjected.
The Oyster Creek reactor vessel was designed and manuf actured in accordance with General Electric Specification 21A1105 and ASME Section I as discussed in Ref erence 13.
The original operating lLnitations were based upon the require-ment that the minista temperature for pressurization be at 1290 134 Am endm on e Vn. d7
I, 3,3-2a least 60*F greater than the nil ductility transformation temperature. The minimum temperature for pressurization at any time in life had to account for the toughness properties in the most limiting regions of the reactor vessel, as well as the ef f ects of f ast neutron embrittlement.
Figures 3.3.1 is derived from an evaluation of the fracture toughness properties performed for Oyster Creek.
(Reference
- 12) in an effort to establish new operating limits. The results of neutron flux dosimeter analyses in Reference 12 indicate that the total fast neutron fluence (>l Mev) expected for Oyster Creek at the end of teggef f ective full power years of operation is 1.22 x 10 avt on the inside surface of the reactor vessel core region shell.
A conservative fast neutron fluence of 75% of this value is assumed at the 1/4 T (one quarter of wall thickness) location for the preparation of the pressure / temperature curves in Figure 3.3.1.
Stud tensioning is considered significant from the standpoint of brittle fracture only when the preload exceed approximately 1/3 of the final design value.
No vessel or closure stud minimum temperature requirements are considered necessary for preload values below 1/3 of the design preload with the vessel depressurized since preloads below 1/3 of the design preload result in vessel closure and average bolt stresses which are less than 20% of the yield strengths of the vessel and bolting materials.
Extensive service experience with these materials has confirmed that the probability of brittle fracture is extremely remote at these low stress levels, irrespective of the metal temperature.
1290 135 Amendment No.
42
3,3-3 The reactor vessel head flange and the vessel flange in combination with the double "0" ring type seal are designed to provide a laak--tight seal when bolted together. When the vessel head is placed on the reactor vessel, only that portion of the head flange near the inside of the vessel rests on the vessel flange.
As the head bolts are replaced and tensioned, the vessel head is flexed slightly to bring together the entire contact surfaces adjacent to the "0" rings of the head and vessel flange. Both the head and the head flan.e have an NDI temperature of 40 F, and they are not subject to any appreciable neutron radiation exposure. Therefore, the minimum vessel head and head flange temperature for bolting the head flange and vessel flange is established as 40 F + 60 F or 100 F.
Detailed stress analyses (') were made on the reactor vessel for both steady state ~and transient conditions with respect to material fatigue. The results of these analyses are presented and compared to allowable stress limits in Reference (4).
The specific conditions analyzed included 120 cycles of normal startup and shutdown with a heating and cooling rate of 100 F per hour applied continuously over a temperature range of 100 F to 546 F and for 10 cycles of emergency cooldown at a rate of 300 F per hour applied over the same range. Thermal stresses from this analysis combined with the primary lead stresses fall within ASME Code Section III allowable stress intensities.
Although the Oyster Creek Unit 1 reactor vessel was built in accordance with-Section I of the ASME Code, the design criteria included in.the reactor vessel specifications were in essential agreement with the criteria subsequently incorporated into Section III of the Code.(6) 1290 136 Amendment No. 42
3.3-6 Chloride stress corrosion tests on stressed 304 stainless steel specimens have been reported (11). According to the data, allowable chloride concentrations could be set over an order of magnitude higher than the established limit of 1.0 ppm at the oxygen concentration (0.2-0.3 ppm) that will be present during power operation. Oxygen is maintained at low levels by the turbine-condenser off-gas system.
Zircaloy does not exhibit similar stress corrosion failures.
Air saturated water (7 ppm oxygen) is pu= ped into the reactor as a result of operation of the control rod drive system.
Therefore, the oxygen level in the reactor water can be higher than 0.2-0.3 ppm during startups or during periods of hot standby when the reactor is not steaming at significant powers, and a more stringant limit of 0.1 ppm chloride has been established for these periods to insure that the combination ofchlorideandoxygenwillplwaysbewellbelowstress corrosion failure limits (11 At reactor steaming rates of at least 100,000 pounds per hour boiling occurs in the reactor causing deaeration of the reactor water which maintains oxygen below operating levels.
In the case of BWR's where no additives are used in the primary coolant, and where neutral pH is maintained, conductivity pro-vides a verv good measure of the quality of the reactor water.
When the conductivity is within its proper normal range, pH, chloride, and other impurities affecting conductivity and water quality must also be within their normal ranges.
Signifi-cant changes in conductivity provide the operator with a warn-ing mechanism so that he can investigate and remedy the condi-tions causing the change. Measurements of pH, chloride, and other chemical parameters are made to determine the cause of the unusual conductivity and instigate proper corrective action.
These can be done before limiting conditions, with respect to variables affecting the boundaries of the reactor coolant, are exceeded.
Several techniques are available to correct off-standard reactor water quality conditions including removal of impurities from reactor water by the cleanup system, reducing input of impurities causing off-standard conditions by reducing power and placing the reactor in the cold shutdown condition.
The major benefit of cold shutdown is to reduce the temperature dependent corrosion rates and thereby provide time for the cleanup system te re-establish proper water quality.
References (1) FDSAR, Volume I, Section IV-2 (2)
(Deleted)
} 2 } f]
] "$ [
(3)
(Deleted )
(4) Liceneing Application Amendment 16, Design Recuirements Section '
(5)
(Deleted )
l (6) FDSAR, Volume I, Section IV-2.3.3 and Volume II, Appendix H (7) FDSAR, Volume I, Table IV-2-1 (8) Licensing Application Amendment 34, Ouestion 14 (9) Licensing Application knendment 28, Item III-B-2 (10) Licensing Application Amendment 32, Ouestion 15 (11) Licensing Application Amendment 11, Ouestion VI-4 (12) Licensing Application Amendment 68, Supplement No. 6, Addendum No. 3 (13) Licensing Application Amendment 16, Page 1 Amendment No, 42
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150 200 250 300 MINIMUM REACTOR VESSEL TEMPERATURE (FAHRENHEIT) 1290 138 OYSTER CREEK NUCLEAR GENERATING STATION REACTOR VESSEL PRESSURE / TEMPERATURE LIMITS FOR UP TO TEN EFFECTIVE FULL POWER YEARS OF CORE OPERATION Figure 3.3.1 Amendment No. 42