ML20148G622
| ML20148G622 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 06/03/1997 |
| From: | Dugger C ENTERGY OPERATIONS, INC. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20148G625 | List: |
| References | |
| W3F1-97-0111, W3F1-97-111, NUDOCS 9706060069 | |
| Download: ML20148G622 (5) | |
Text
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y Enttrgy Operations, Inc.
Killona, LA 70066-0751 Tel 504 739 6000 Charles M. Dugger vc res ent. Operatms W3F1-97-0111 A4.05 PR June 3,1997 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555
Subject:
Waterford 3 SES Docket No. 50-382 License No. NPF-38 Supplement to Technical Specification Change Request NPF-38-179 Gentlemen:
Technical Specification Change Request NPF-38-179 was submitted under letter W3F1-96-0045 on July 17,1996. This supplement to Technical Specification Change Request NPF-38-179 was developed to provide you with updated information based on continuing reviews and an improved calculation method.
Technical Specification Change Request NPF-38-179 requests the minimum required level in the condensate storage pool (CSP) be increased from 82 percent to 91 percent to account for vortexing and instrumentation measurement uncertainties.
Subsequent to the submittal of July 17,1996, it has been determined that the short term requirements for the component cooling water (CCW) makeup system were not considered in the design bases of the CSP. In addition, the calculation for vortexing has been updated using a calculation method obtained from ABB-Combustion
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Engineering Nuclear Operations and a new instrument measurement uncertainty
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was identified relating to ventilation system operation.
During a tornado, LOCA, or seismic event, the CCW, Essential Chilled Water, and
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I Emergency Diesel Generator Jacket Water systems will require makeup due to possible system leakage and/or to account for evaporative losses. The CCW makeup system, which takes suction from the CSP, will automatically provide this l
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Supplement to Technical Specification Change Request NPF-38-179 W3F1-97-0111 i
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June 3,1997
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. makeup. To account for the short term CCW makeup system requirements an
. additional amount of CSP water is required. The amount of CSP water required by i
the CCW makeup system has been determined to be less than 3.8 percent CSP J
level.
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Piping support modifications are required to insure the availability of the Fuel Pool l
Purification Pump Fuel Pool Suction isolation Valve, FS-309, following a seismic 1
' event. This valve is credited for being available during the event to isolate leakage from the Spent Fuel Pool. The availability of FS-309 was assumed when determining short term CCW Makeup System requirements (less than 3.8 percent CSP level). The required piping support modifications will be completed prior to l
entering Mode 4 following Refuel 8.
The vortexing calculation has been updated and indicates that 1.53 percent CSP L
level is required to prevent vortexing. This is less than the 5.7 percent stated in the July 17,1996 submittal. A different calculation method, obtained from ABB-Combustion Engineering Nuclear Operations when they evaluated vortexing for the i
Refueling Water Storage Pool (RWSP), was used to determine the new value.
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Attachment A contains the original vortexing calculation (EC-M95-012, Rev. 0) used t
in the development of the July 17,1996 submittal. This calculation utilized a
" submergence versus velocity" curve obtained from Goulds Pump Manual Section
.16B-3. The curve, however, did not cover velocities less than 1.5 ft/sec. The i
velocity of the flow to the Emergeny Feedwater System from the CSP was calculated to be 0.71 ft/sec. Because the calculated velocity was below the minimum velocity covered by the " submergence versus velocity" curve (Figure 5 in attachment l_
A), it was conservatively assumed that maintaining the strainer se5 merged would prevent vortexing. This value, including a two inch margin, was determined to be 1.2 i
l ft, which corresponds to 5.7 percent CSP level.
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Attachment B contains portions of the revised vortexing calculation (EC-M95-012, l
Rev.'1 CN#1) used in the development of this supplement. (The portions of this 1
i-calculation addressing the BAM Tanks, EDG Oil Storage and Feed Tanks, RWSP and VCT are not included in the attachment.) This calculation utilizes an analytical I
method used in the ABB-Combustion Engineering Nuclear Operations evaluation of i
Waterford-3 RWSP vortexing. The revised CSP calculation uses a sink-flow model d
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Supplement to Technical Specification Change Request NPF-38-179 W3F1-97-0111 Page 3 June 3,1997 i
utilizing a Froude Number assuming no rotation, since there are no disturbances in the CSP (such as columns) to initiate rotational flow. The Froude Number formula L
used in this calculation is an accurate approximation of the Froude Number determination methodology used in Reg. Guide 1.82. The resulting CSP critical j
height is 0.32 ft, which corresponds to a liquid level of 1.53 percent. It should be l
noted that, had the " submergence versus velocity" curve (Figure 5 in attachment A) l
~ been extrapolated to a velocity of 0.71 ft/sec, the resulting critical height would have
-l approximated the critical height calculated using the analytical method obtained from ABB-Combustion Engineering Nuclear Operations.
The instrumentation measurement uncertainty of 4.46 percent used in the July 17,
-l 1996 submittal is being increased by 0.5 percent to 4.96 percent CSP level to i
account for ventilation system affects on CSP level indication. As discussed in LER i
97-007, RWSP level indication was discovered to be affected by ventilation system operation. As part of the follow-up investigation, the CSP was identified as being susceptible to the same type of error. The Plant Monitoring Computer indication for i
CSP level was observed to increase by 0.5 percent when the Reactor Auxiliary l
Building normal ventilation system was placed in service.
j The 91 percent minimum CSP level requested in the July 17,1996 submittal remains
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valid. This level is based on having at least 170,000 gallons available (80.71 l
- percent) while accounting for the required level to prevent vortexing (1.53 percent),
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instrumentation measurement uncertainties (4.96 percent), and short term requirements for the CCW makeup system (less than 3.8 percent). Atachment C provides a visual representation of the differences between the original submittal and this supplement.
' A revised Bases for Technical Specification 3/4.7.1.3 is provided in Attachment D.
The Bases has been revised to discuss the short term requirements for the CCW makeup system and to clarify that the.170,000 gallons is for emergency feedwater.
The attached Bases also contains changes previously made under 10CFR50.59.
The changes made under 10CFR50.59 are editorialin nature and help clarify the Bases. These changes include deleting the reference to 350 F, using the term
" ultimate heat sink" instead of " cooling towers", referring to the " tornado event" instead of " accident", and moving the " natural circulation" reference to include it in '
the discussion of BTP RSB 5-1.
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Supplement to Technical Specification Change Request NPF-38-179 l
. W3F1-97-0111 I
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' Please replace the Bases page provided with the July 17,1996 submittal with the Bases page provided in Attachment D.
The values accounting for vortex prevention and instrumentation measurement.
j uncertainties that were discussed in the July 17,1996 submittal have changed as l
described above. In addition, the short term requirements of the CCW makeup water j
system have been accounted for as described above. However, the original Safety l
Analysis and Safety and Significant Hazards Determination, provided with the July 17,1996 submittal, remain unchanged and require no revisions. Increasing the minimum required CSP level to 91 percent will ensure that at least 170,000 gallons is i
available for use by the emergency feedwater system.
Should you have any questions or comments concerning this request, please contact Mr. Paul Caropino at (504) 739-6692.
Very truly yours, l
i f
YY C. M. Dugger Vice President, Operations l
Waterford 3
. CMD/DBM/ssf Attachments:
Affidavit TS Pages
'cc:
E.W. Merschoff, NRC Region IV D.P. Patel, NRC-NRR J. Smith N.S. Reynolds -
NRC Resident inspectors Office Administrator Radiation Protection Division (State of Louisiana)
American Nuclear Insurers I
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i UNITED STATES OF AMERICA -
l NUCLEAR REGULATORY COMMISSION 4
In the matter of
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1 Entergy Operations, incorporated
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Docket No. 50-382 i
Waterford 3 Steam Electric Station
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l-Charles Marshall Dugger, being duly sworn, hereby deposes and says that he is Vice l
President Operations - Waterford 3 of Entergy Operations, incorporated; that he is duly i
j authorized to sign and file with the Nuclear Regulatory Commission the attached
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' Supplement to Technical Specification Change Request NPF-38-179; that he is familiar
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with the content thereof; and that the matters set forth therein are true and correct to the best of his knowledge, information and belief.
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Charles Marshall Dugger 0Y
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Vice President Operations - Waterford 3 l
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STATE OF LOUISIANA
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Subscribed and sworn to before me, a tary Public in and for the Parish and State above named this a C day of wa
.1997.
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C LM j-Notary Public i
My Commission expires acA<X[.
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