ML20002A329
| ML20002A329 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 04/21/1976 |
| From: | Vandenburgh D YANKEE ATOMIC ELECTRIC CO. |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| WYR-76-48, NUDOCS 8011110773 | |
| Download: ML20002A329 (5) | |
Text
L Propored Changa No. 137
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;S Tcliphone 617 366-90ll j',.o 710 390 0739
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YANKEE ~ ATOMIC ELECTRIC COMPANY
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,'20 Tuin Road Westborough, Massachusetts 01581
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United States Nuclear Regulator mmission f # 4.aesarme Washington, D. C.
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Reference:
License No. DPR-3 (Docket No. 50-29)
Dear Sir Pursuant to Section 50-59 of the Commission's Rules and Regulations Yankee Atomic Electric Company hereby proposes the following modification to Appendix A to the Technical Specifications.
PROPOSED CHANGE: We propose adding a pulsation dampener on the three (3) charging pump discharge header. The design and operation cf the Charging and Volume Control System is described in Section 203 of the Facility Hazards Summary Report (FHSR).
We have revised page 203:1 and drawing No. 646J430 (inserted af ter page 203:1) and added page 203:lA to incorporate the proposed change.
Copies of the revised pages and the drawing are attached.
REASON FOR CHANGE: The installation of the pulsation dampener will hopefully eliminate vibrations now being experienced o.
the discharge header.
SAFETY CONSIDERATIONS: The Proposed Change does not present any signi-cant hazards consideration not described or implied in the reference license as amended.
The proposed change has been reviewed by the Nuclear Safety Audit and Review Committee.
SCHEDULE OF CHANGE: The change will be effected following Commission approval.
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United St2t;': Nucicr Regulntory Commir::: ion April 21, 1976 Attn: Office of Nuclear Reactor Regulation Page Two We trust you will find this information satisfactory; however, should you desire additional information, please do not hesitate to contact us.
Very truly yours, YANKEE A'IOMIC ELECTRIC COMPANY D. E. Vandenburgh Vice President COMMONWEALTH OF MASSACHUSETTS)
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COUNTY OF WORCESTER
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Then personally appeared before me, D. E. Vandenburgh, who being duly sworn, did state that he is Vice President of Yankee Atomic Electric Company, that he is duly authorized to execute and file the foregoing request in D e name and on the behalf of Yankee Atomic Electric Company, and that the t*atements therein are true to the best of his knowledge and belief.
M Armand R.
Soucy Notary Public My Comnission Expires September 9, 1977 f
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203:1 DRAFT 203 CHARGING AND VOLUME CONTROL SYSTEM Ceneral The ch'arging and volume control system is an auxiliary system in the primary plant and is designed to accomplish the following major functions:
Water charging to the main coolant system Water removal from the main coolant system Boric acid addition and removal for control purposes Quenching of relief and safety valve discharge Pressurizer vessel cooling ar.d decontamination Noncondensible gas removal Chemical addition Water charging to auxiliary system and equipment The arrangement of the charging and volume control system is shown on drawing No. 646-J-430.
It contains the following major items of equipment, designed in accordance with the following codes:
Equipment
- ASME Section VIII - 1956 - Unfired Pressure Vessels Piping
- ASA 31.1 - 1955 - Code for Pressure Piping, Sections 1 and 6 Valves, Fittings - ASA B16.5 - 1953 - Code for Steel Piping and Flanged Fittings High Pressure Charging Pumps Three motor driven positive displacement charging pumps are provided in the charging and volume control system.
The capacity of each pump is approxi-mately 33 gpm, when operating against a discharge head of 2,100 psi gage. Two of the' pumps serve as a spare for the other, and they can be operated singly or simultaneously, if required. Any pump can be isolated from the system for re-pairs. Two of the pumps are driven throegh variable speed fluid couplings, so that their flow can be controlled between 11 and 33 gpm.
Pump No. 3 may be used in conjunction with the loop fill and chemical injection line to accomplish charging to any isolated loop while one or both of the other charging pumps is servicing the reactor vessel portion of the main coolant system.
All of the high pressure charging pumps are provided with a pressure relief valve.
Pulsation Dampener A homogeneous chrome moly pulsation dampener is installed on the I
discharge of Number 3 charging pump. It serves to reduce the pressure variation created by the variable speed pump and is employed to reduce fatigue stressing. The dampener basic operation consist of absorbing the potential energy of the pressure shock by the compression of a bladder precharged with nitrogen.
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203:lA DRAFT Feed and Bleed Heat Exchanger The feed and bleed heat exchanger consists of a set of four small individual heat exchangers connected in series, which cool the bleed before it is reduced in pressure. Multiple exchangers are employed in order to reduce the size of metal parts and the corresponding high thermal stresses that may occur during severe thermal transient operation.
The bleed flows through the tubes while the feed is passed through the shell side, thus recovering some of the heat otherwise lost in a bleeding process.
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fJRC ronu 195 u.S. NUCLE AR RESULATCRY COMMI,. >N DOCKET NUM BE R f
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NRC DISTRIBUTION rOn PART 50 DO':KET MATERIAL TO:
FROM: YANKEE AT0!qC ELECTRIC CO DATE OF DOCUMtiNT WESTBOROUGH, MASS 9-Al-1(o NRC DATE RECEIVED D E VANDENBURGH
- %- Ab' gd NE TTE R MTORIZED PROP INPUT FOP.M NUMBER OF COPIES RECEIVED bnfOtNAL
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DESCRIPTION E NCLOSU RE LTR NOTORIZED 4-21-76..........
LTR WITH PROPOSED CHANGE NO 137 TO THE TECH SPEC TO ADD A PULSATION DAMPENER ON 3 CHARG-
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ING PUMP DISCHARGE IEADER... ALSO PROVIDING REVISED PAGES(203:$fD DRAWING NO. 646J430 DO NOT REMOYE i
ACKNOWLEDGED' PLANT NAME: AAhE_EE Owe SAFETY
- FOR ACTION /INFORMATION ENVIRO L4 o'ifi- % Rk'R l
ASSIG5ED AD :
ASSIGNED AD :
- BRANCll CllIEF :
k geLE BRANCll CHIEF :
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PROJECT MANAGER :
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INTERNAL DISTRIBUTION REG FILED SYSTEUS_ SAFETY PLANT SYSTFMM vm7 Tun qcy
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SCIIROFDER BENAROYA B.ATLARD 2
Wf_QELD LAINAS SPANGLER COSSICK & STAFF EJGIEEEE EG IPPOLITO filfC MAccARy SITE TECH CASE KNIGHT OPERATING REACTORS GAMMILL J Ml%UER SIHWEIL STELLO STEPP
_W2LESS PAULICKI HUDiAN OPERATING TECH PROJECT MANAGEMENT REACTOR SAFETY
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EISENHirr SITE ANALYSIS BOYD ROSS
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SHA0 VOLLMER P. COLLINS
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1100STON ROSZTOCZY N ~BAER BUNCH SCHWENCER X
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PETERSON CHECK
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GRIMES
'KREGER MELTZ
!!ELTEMES AT & I SITE _SAlliTY & ENVIRC 3KOVHOLT SALTZMAN ANALYSIS RUTBERG DENTON & MULLER EXTERNAL DISTRIBUTION CONTROL NUMBER
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Meeting Notice for Yankee-Rowe 2~-
May 12, 1976
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cc: NRC PDR G. Knighton
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R. Tedesco R. Fralcy, ACRS(16)
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D. Eisenhut OISE(3) 3 V. Moore OELD
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.W. Gammill' Principal Staff Participants
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P. Collins t
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T. B. Abernathy, TIC
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R. liouston J. R. Buchanan, NSIC T.~Speis
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P. Check
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T. Novak Z. Ros:toczy V. Benaroya G. Lainas T. Ippolito D. Ziemann-
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