ML20248H264
| ML20248H264 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 10/04/1989 |
| From: | GENERAL PUBLIC UTILITIES CORP. |
| To: | |
| Shared Package | |
| ML20248H255 | List: |
| References | |
| NUDOCS 8910110238 | |
| Download: ML20248H264 (12) | |
Text
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n ATTACHMENT Technical Specification Changes 31013989 8910110238 891004 ADOCK0500g{,6],
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3.1.7 MODERATOR TEMPERATURE COEFFICIENT OF REACTIVITY l
Applicability Applies to maximum positive moderator temperature coefficient of reactivity at full power conditions.
Objective To assure that the moderator temperature coefficient stays within the limits calculated' for safe operation of the reactor.
Specification 3.1.7.1 The moderator temperature coefficient shall not be positive at power levels above 95% of rated power.
3.1.7.2 The moderator temperature coefficient shall be < +0.9 x l
10-* Ak/k/F at power levels 5 95% of rated poweE Bases A non-positive moderator coefficient at power levels above 95% of rated power is specified such that the maximum clad temperatures will not exceed the Final Acceptance Criteria based on LOCA analyses.
Below 95% of rated power the Final Acceptance Criteria will not be exceeded with a positive moderator temperature coefficient of
+0.9 x 10-* Ak/k/F. All other accident analyses as reported in the l
FSAR have been performed for a range of mcderator temperature coefficients up to and including +0.9_ x 10-* Ak/k/F.
l A non-positive moderator coefficient at power levels above 95% of rated power is also required to prevent overpressurization.of the reactor coolant system in the event of a feedwater line break (see Specification 2.3.1, Basis C, Reactor' Coolant System Pressure).
The experimental value of the moderator coefficient will be corrected to obtain the hot full power moderator coefficient.
The Final Acceptance Criteria states that post-LOCA clad temperature will not exceed 2200*F.
f REFERENCES (1) UFSAR, Section 14 (2) UFSAR, Section 3 3-16 Amendment No. 45 (9-22-78)
The quantity of boric acid in storage from either of the three above mentioned sources is sufficient to borate the reactor coolant system to a one percent subcritical margin in the cold condition at the worst time in core life with a stuck control rod assembly. Minimum volumes (including a 10 percent safety factor) of 906 ft of 8700 ppm boron as concentrated boric acid solution in the boric acid mix tank or in a reclaimed boric acid storage tank or approximately 40,000 gallons of 2270 ppm boron as boric acid solution in the l
borated water storage tank (*) will each satisfy this requirement.
The specification assures that at least two of these supplies are available whenever the reactor is critical so that a single failure will not prevent boration to a cold condition. The minimum volumes of boric acid solution given include the boron necessary to account for xenon decay.
The primary method of adding boron to the reactor coolant system is to pump the concentrated boric acid solution (8700 ppm boron, minimum) into the makeup tank using either the 10 gpm boric acid pumps or the 30 gpm reclaimed boric acid pumps. Using only one of the two 10 gpm boric acid pumps, the required volume can be injected in less than 13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br />. The alternate method of addition is to inject boric acid from the borated water storage tank using the makeup and purification pumps. The 40,000 gallons of boric acid can be injected l
in less than four hours using only one of the makeup and purification pumps.
Concentration of boron in the boric acid mix tank or a reclaimed boric acid storage tank may be higher than the concentration which would crystallize at ambient conditions.
For this reason, the boric acid mix tank is provided with an immersion electric heating element and the reclaimed boric acid tanks are provided with low pressure steam heating jackets to maintain the temperature of their contents well above (10 F or more) the crystallization temperature of the boric acid solution contained in them. Both types of heaters are controlled by temperature sensors immersed in the solution contained in the tanks.
Further, all piping, pumps and valves associated with the boric acid mix tank and the reclaimed boric acid storage tanks to transport boric acid solution from them to the makeup and purification system are provided with redundant electrical heat tracing to ensure that the boric acid solution will be maintained 10nF or more above its crystallization temperature. The electrical heat tracing is controlled by the temperature of the external surfaces of the piping systems. Once in the makeup and purification system, the boric acid solution is sufficiently well mixed and diluted so that normal system temperatures assure boric acid solubility.
References 1
(1) UFSAR, Sections 9.1 and 9.2 l
l (2) UFSAR, Figure 6.2 (3) Technical Specification 3.3 3-20 Amendment No. 50 (March 16, 1979)
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- 1. -The protection system reactor power / imbalance envelope
.. trip setpoints shall be reduced 2 percent in power for each 1 percent tilt, in excess of the tilt limit, or when thermal power is equal to or less than 50% full i
power with four. reactor coolant pumps running, set the nuclear' overpower trip setpoint equal to or less than 60% full power.
2.
The control. rod group withdrawal limits in the CORE OPERATING LIMITS REPORT shall be reduced 2 percent in power for each 1 percent tilt in excess of the tilt limit..
- 3. ~ The operational imbalance limits in'the CORE OPERATING
~ LIMITS REPORT shall be reduced 2 percent in power for each 1' percent tilt in excess of the tilt limit.
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- f. Except for physics or diagnostic testing, if quadrant tilt
. is -in excess of the maximum tilt limit defined in the CORE' OPERATING LIMITS REPORT and using the applicable detector system defined in 3.5.2.4.a, b, and c above, the reactor will be placed-in the HOT SHUTDOWN condition. Diagnostic testing during power operation with a quadrant tilt is permitted provided that the thermal power allowable is restricted as stated in 3.5.2.4.d above.
- g. Quadrant tilt shall be monitored on a minimum frequency of once every two hours during power operation above 15 percent of rated power.
3-34a Amendment No. 29, 38, 39, 40, 45, 50, 120, 126, 142, 150
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'3.8.9 The reactor buil' ding purge sys' tem,' including the radiation:
3 monitors which initiate purge isolation,'shall.be ' tested and L
verified to be operable no more than one week prior to l'
refueling operations.
3.8.10 ? Irradiated fuel shall' not be removed from the reactor until.
.the unit has been suberitical' for at least 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
Bases Detailed written procedures will be available for use by refueling
, personnel. These procedures, the above specifications, and the l--
design of the~ fuel handling equipment as described in Section 9.7 of the FSAR incorporating. built-in interlocks and safety features,.
L provide assurance that no incident could occur during the refueling operations that would result in a hazard to public health and safety.
If no change is being made in. core geometry, one' flux.
monitor is sufficient. This permits maintenance on the instrumentation. Continuous monitoring of radiation levels and neutron flux provides immediate indication of an unsafe condition.
The' decay heat removal pump is used to maintain a uniform boron concentration. (1) The shutdown margin indicated in Specification l
3.8.4 will keep the core subtritical, even with all control rods withdrawn from the core. (2) The boron concentration will be l
sufficient to maintain the core k.,, < 0.99 if _ all the control rods were removed from the core, although only a few control rods will be l
removed at any' one time during fuel shuffling and replacement. The keff with all rods'in the core and with refueling boron. concentration is~ approximately 0.9.. Specification 3.8.5 allows the control room operator to inform the reactor building personnel of any impending unsafe condition detected from the main control board indicators during fuel movement.
The specification requiring testing Reactor Building purge termination.is to verify that these components will function as required should a fuel handling accident occur which resulted in the release of significant fission products.
Specification 3.8.10 is required as the safety analysis for the fuel handling accident was based on the assumption that the reactor had been shutdown for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. (3)
REFERENCES (1) UFSAR, Section 9.5 (2) UFSAR, Section 14.2.2.1 (3) UFSAR, Section 14.2.2.1.2 3-45
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LOCA LIMITED MAXIMUM ALLOWABLE LINEAR HEAT RATE TMI-1 Figure 3.5-2M AmendmentNo.1/2
4 Affidavit Certifying Proprietary Nature of BAW-2001P 4
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4 AFFIDAVIT OF JAMES H. TAYLOR
- A;.My name is. James H. Taylor.
I am Manager of Licensing Services at The L
mWk & Wilcox company, a participating ii==iver in the mWk & Wilcox Utility Owners Group (B&WOG) and as such I am authorized-to execute this Affidavit.
B.
I am. familiar with the cLiteria applied by,the Nuclear Regulatory Commission (NRC) to determine whether certain information of the B& NOG is
- proprietary.
C.
In detenninirg whether a B&WOG document is to be designated as proprietary 7
information, an initial determination is made by the. Unit Manager who is responsible for originating the document as to' whether it falls within the -
. criteria set forth in Paragraph D hereof.
If the information falls within any one of these criteria, it is designated as proprietary by the originating Unit Manager.. This initial. determination is reviemd by the cognizant manager at the next higher organizational level.. If the den =nt.
is designated as proprietary, it is reviewed again by me to assure that the regulatory requirements of 10 CFR Section 2.790 are met.
D; 'The following information is pInvided to demonstrate that the provisions of 10 CFR Section 2.790 of the h4naion's regulations have been considered:
(i)
The'information has been held in confidence by the B&WOG. Copies of the document are clearly identified as proprietary.
(ii)
The following criteria are customarily applied by the B&WOG in a rational decision process to determine whether the information should be designated as proprietary.
Information may be designated as proprietary if one or more of the following criteria are met.
a.
Information reveals cost or price information, w.umuial I
strategies, production capabilities, or budget levels of the B&WOG or its suppliers.
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b.
'Ihe information reveals data or material concerniry the B& NOG research or development plans or pxwicms of present or potential econcmic advantage to the B&WOG.
c.
The use of the information by a non-maber would decrease his experrlitures, in time or resources, in designing, producing, or marketirg a similar product.
d.
'1he information consists of test data or other similhr data cci,xrning a process, method or wurnent, the application of which results in an economic advantage to the B&WOG.
e.
'Ibe 'information reveals special aspects of a process, method, wuponent or the like, the exclusive use of which results in an ecusihic advantage to the B&WOG.
f.
The information contains ideas for which patent protection may be sought.
'Ihe document (s) listed on Exhibit "A", which is attached hereto and made a part hereof, has been evaluated in accordance with the B&WOG procedures with respect to classification and has been found to contain information which falls within one or more of the criteria enumerated above.
Exhibit "B", which is attached hereto and made a part hereof, specifically identifies the criteria applicable to the document (s) listed in Exhibit "A".
(iii) 'Ihe document (s) listed in Exhibit "A", which has been made available to the United States Nuclear Regulatory commission was made available in confidence with a request that the document (s) and the information contained therein be withheld from public disclosure.
(iv)
'1he information is not available in the open literature and to the best of our knowledge is not known by other organizations with interests and activities similar to those of the B& HOG.
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(v)'
Specific information with regard to whether public disclosure of the
'information is likely.to cause economic harm to the position of the B&WOG, taking into account the value ' of the information to the B&WOG;:.the amount of effort or money expended by the B&WOG developing the information; and the ease or difficulty with which the information could be properly duplicated by others is given in Exhibit "B".
E.
I have personally reviewed the dent (s), listed on Exhibit "A" and have found that it.is considered proprietary by the B&WOG because it ocntains information which falls within one or more of the criteria enumerated in' Faragraph D, and it is information which is customarily held in confidence and ' protected as proprietary information by the B&WOG.
'Ihis report comprises information utilized by the B&WOG in its business'which afford the B&WOG an uwurtunity to obtain an ecancanic advantage over those who may wish to kncw or use the information contained in the document (s).
J' Nb b
JamesH.Taylp[
State of Virginia)
)
SS. Lynchburg City of Lynchburg)
James H. Taylor, being duly sworn, on his oath deposes and says that he is the person who subscribed his name to the foregoing statement, and that the matters and facts set forth in the statement are true.
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'amesH. Taylor /
J Subscribed and sworn bpforp me this 47./f day of L&dev 1989.
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V Notary Public in and for the City of Lynchtmrg, State of Virginia My ocumissian Expires h'd O M%
s Exhibit A
.o Low Pre-Pressure Fuel Rod Program Burnup Extension LOCA Analysis BAW-2001P June 1987
Exhibit B o
Description of Material Apolicable Criteria Low Pre-Pressure Fuel Rod Program b,c Burnup Extension LOCA Analysis BAW-2001P June 1987 i
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