ML20215E722

Discusses Cancellation of Mods to Torus Pool Thermal Mixing & Local Suppression Pool Temp Monitoring at Electromatic Relief Valve Quenchers or Discharge Headers.Supports Cancellation of Torus Mods

ML20215E722
Person / Time
Site:	Oyster Creek
Issue date:	10/01/1986
From:	Donohew J Office of Nuclear Reactor Regulation
To:	Fiedler P GENERAL PUBLIC UTILITIES CORP.
Shared Package
ML20215E725	List: ML20215E722 ML20215E726
References
TAC-60152, TAC-60153, NUDOCS 8610150473
Download: ML20215E722 (4)

Text

'

/potenq) UNITED STATES 2 .n r ' go NUCLEAR REGULATORY COMMISSION

' WASHINGTON, D. C. 20555 r, y October 1, 1986

%y Docket No. 50-219 Mr. P. B. Fiedler Vice President and Director-Oyster Creek Nuclear Generating Station Post Office Box 388 Forked River, New Jersey 08731

SUBJECT:

TORUS POOL THERMAL MIXING AND LOCAL TEMPERATURE INDICATION -

CANCELLATION OF MODIFICATIONS (TAC 60152, 60153)

Re: Oyster Creek Nuclear Generatino Station By letter dated October 31, 1985, you proposed to cancel two modifications to provide (1) local suppression (torus) pool temperature monitoring at the electromatic relief valve cuenchers, or discharae headers, in the pool and (2) thermal mixing for the pool near the quenchers. You consider these modi-fications are part of the scope of work required by the Confirmatory Order,

" Modification of the January 13, 1981 Order and December 29, 1981 Order", dated January 19, 1982. This Order is related to the Mark I Containment Lono Term Program (LTP) and would reouire these modifications to be completed before the restart from the Cycle 11 Pefueling (Cycle 11R) outage. The Cycle 11R outace began in April 1986 and is scheduled to end in October 1986.

The Mark I Containment LTP Confirmatory Order dated January 19, 1982, reovires only plant modifications needed to comply with the Acceptance Criteria in Appendix A of NUREG-0661, Mark I Containment long-term Program, dated July 1980. The applicable Acceptance Criteria for the above torus modifications is the local suppression pool temperature limit for safety relief valve dis-charge loads in Appendix A. Because for Oyster Creek the maximum local to bulk suppression pool temperature is 43*F and the maximum allowed bulk temperature is 95 F in the Technical Specifications, the maximum local temperature is less than the 200*F Acceptance Criteria in Appendix A. It is less than the 160 F criteria in the Bases of Section 3.5 of the Oyster Creek Technical Specifications.

These madifications were also not addressed in the staff's two Safety Evaluations (SE) on the Mark I Containment LTP dated January 13, 1984. We, therefore, conclude that these modifications are not needed, and were not needed, to meet the Acceptance Criteria of NUREG-0661 and, therefore, are not part of the modifications required by Confirmatory Order dated January 19, 1982.

The above modifications are not part of the licensee's modification to monitor The the torus bulk water temperature in accordance with NUREG-0661 and 0783.

latter modification for torus bulk water temperature is part of the staff's long-term Mark I Containment Review and Confirmatory Order dated January 19, 1982. You requested in your letter dated July 26, 1985, to defer this latter 8610150473 e61001 PDR ADOCK 05000219 ,

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October 1, 1986 P. B. Fiedler -2 modification (Item 6 of your letter) from the Cycle 11R outaoe to Cycle 12R outage. This de' cision will be the subject of a separate letter to you later on your July 26, 1985, request.

In the meeting of April 10, 1986, we presented a Request for Additional Informa-

' tion (RAll on this subject. The RAI had ouestions on (1) the applicability of.

your request to cancel these torus modifications to the Acceptance Criteria in NUREG-0661, Mark I Containment Long-Term Program dated July 1980 and (2) the relationship between the initial suppression pool temperature for the design basis Loss-of-Coolant Accident (LOCA) analysis and the pool temperature limits in the Oyster Creek Technical Specifications (TS). These RAI were sent to you in our letter dated May 5, 1986.

Your responses to our RAI dated Fay 5,1986,Inonthese this subfect are your letters responses, you stated dated June 16, July 22, and August 4, 1986.

' that without these pool modifications the lo' cal pool temperature will not exceed the limits dictated by the Acceptance Criteria of NUREG-0661 during the most severe relief valve transients of interest and that the initial suppres-sion pool temperature is consistent with the temperature limits in TS and that net positive suction head exists for the core spray system pumps which drav suction from the suppression pool durino a LOCA. The resolution of our con-

' cerns on the initial suppression pool temperature was addressed in our letter to you dated October 1, 1986.

4 In your October 31, 1985, letter, you stated to support your request that the PWR Owner's Groep General Electric (GE) NE00-30832 report, " Elimination of f

Limit on PWR Suppression Pool Temperature on SRV (Safety Relief Valvel Dis-charge with Ouenchers" dated December 1984, concluded that unstable steam condensation is not a concern where quenchers, versus straight pipe discharoe

! headers, are used on SRV discharge piping. You stated that ouenchers have been installed at Oyster Creek, that the NED0-30839 report is applicable to Oyster

" Creek and that the NEDO-30832 report concludes that significant The unstable steam above two condensation and dynamic loads will not occur with quenchers.

modifications were for the operators to be able to monitor the local pool

' temperatures in the vicinity of the cuenchers and provide additional thermal i

mixing at the quenchers to prevent the onset of unstable steam condensation at the cuenchers during SPV discharges to the torus and the resulting dynamic load and possible damage to the SRV discharge piping and torus.

The staff has started its review of NED0-30832. report but will not complete its detailed review before your scheduled restart from the Cycle 11R outace in October 1986.

As discussed in the enclosed Safety Evaluation rel:'.ed to i

this action, the staff has concluded that there is a sufficient basis for agreeing to your cancellation of these modifications without review of NEDO-30832 because we conclude that the modifications are not needed fo safe operation of Oyster Creek.

2 h

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r P. B. Fiedler October 1, 1986 Based on the above, we conclude that these torus modifications are not required as part of the Mark I long-term Program Confirmatory Order and are not needed for the safe operation of Oyster Creek. Therefore, we agree to your proposed cancellation of these torus modifications.

Sincerely,

,r *:12 $

Q N. Donohew, J I., Project Manager

(( Jac BWR Project Directorate #1 Division of BWR Licensing

Enclosure:

Safety Evaluation cc w/ enclosure:

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s' Mr. P. B. Fiedler Oyster Creek Nuclear Dyster Creek Nuclear Generatino Station Generatina Station cc: Resident Inspector Mr. Ernest L. Blake, Jr. '

Shaw, Pittman, Potts and Trowbridna c/o U.S. NRC 1800 M Street, N.k'. Post Office Rox A45 Washinoton, D.C. 20036 Forked River, New Jersey 08731 J.B. Liberman, Esquire Commissioner Bishoo, Liberman, Cook, et al. New Jersey Department of Energy 1155 Avenue of the Americas 101 Conmerce Street New York, New York 10036 Newark, New Jersey 07107 Mr. David Scott, Acting Chief Regional Administrator, Reaion I Bureau of Nuclear Enaineerina U.S. Nuclear Regulatory Commission Department of Environmental Quality 631 Park Avenue 380 Scotch Road Kina of Prussia, Pennsylvania 19406 Trenton, New Jersey 08628 PWR Licensinc Manacer GPU No.iear 100 Interpace Parkway Parsippany, New Jersey 07054 Deouty Attorney General State of New Jersey Department of Law and Public Safety 36 West State Street - CN ll?

Trenton, New Jersey 08625 Mayor lacey Trwnship 818 Wert Lacey Road -

Forked River, New Jersey 08731 Mr. D. G. Holland Licensino Manaaer Oyster Creek Nuclear Generatina Station Post Office Box 388 Forked River, New Jersey 0873)

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