ML20137F653

Summary of 850731 & 0801 Site Meetings W/Util Re Status of Radiological Effluent Tech Specs & Licensing Actions.List of Attendees & Licensee Presentation Encl

ML20137F653
Person / Time
Site:	Oyster Creek
Issue date:	08/22/1985
From:	Donohew J Office of Nuclear Reactor Regulation
To:	Office of Nuclear Reactor Regulation
References
NUDOCS 8508270040
Download: ML20137F653 (10)

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& UNITED STATES E ', NUCLEAR REGULATORY COMMISSION E . $ . .-- [ ,% WASHINGTON D. C. 20555

\((,4 August 22, 1985 1 Docket No.: 50-219 LICENSEES: GPU Nuclear Corporation Jersey Central Power and Light Company FACILITY: Oyster Creek Nuclear Generating Station

SUBJECT:

JUNE 1985 PROGRESS REVIEW MEETING ON LICENSING ACTIONS On Wednesday, July 31, and Thursday, August 1,1985, meetings were held at Oyster Creek Station site with GPU Nuclear (the licensee) to discuss the following: status of the Radiological Effluent Technical Specifications (RETS)

(July 31 and August 1) and status of station licensing actions (August 1).

Attachment 1 is the list of the individuals attending the meetings. Attachment 2 is a copy of the material presented by the licensee at these meetings.

Reference will be made to the Cycle 11 Refueling (Cycle 11R) outage which is currently scheduled to begin in April 1986. The following is a sunnary of the significant items discussed and the actions taken or proposed.

. 1.0 Radioloaical Effluent Technical Specifications (RETS)

The licensee, by letter dated October 22, 1984, proposed changes to the Appendix A Technical Specifications (TS) of Oyster Creek which pertained 4 to the Radiological Effluent Technical Specifications (PETS) required by Appendix I to 10 CFR Part 50. These are changes to existing Sections 3.6 and 4.6 of the TS and to add new Sections 3.14, 3.15, 4.15, and 4.16 to the TS. The staff is now prepared to issue the proposed RETS and the licensee requested that a meeting be held at the Oyster Creek Station site to discuss when the RETS should be effective. Attachment 2 is a handout on the problems the licensee has in implementing the RETS at this time.

The licensee stated that it will need more time, for the RETS to be effective after the date they are issued, than the 90 days requested in its letter of October 22, 1984 The licensee stated that it will need more than a year, until the plant restarts from the Cycle 11 Outage, to develop the software for the Offsite Dose Calculation Model (0DCM); however, all the data needed for the ODCM is being collected by the licensee now.

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The licensee indicated that the primary pathways for exposure to the ropulation and individuals through the liquid discharge pathway are consumption of fish, consumption of shellfish and shoreline exposure.

Drinking water is not an exposure pathway because liquid effluents are discharged into salt water. The cooling water for the station is ocean water from Barnagot Bay and this water does not seep into wells.

The licensee stated that equations must be developed for exposure through the liquid pathway. The present TS on liquid effluents are in terms o' curies released, not exposure to the population or to individuals. The licensee stated that the existing TS are less restrictive or liquid effluents than the proposed RETS.

The licensee agreed that it could implement most of the proposed limiting conditions for operation (LCOs) once the procedures were written. The licensee also agreed that the 90 days, requested in its letter proposing the RETS, would begin August 1, 1985 for those LCOs. The only LCOs the licensee stated it would not implement within the 90-day period were those referencing the ODCM. This would mean that the licensee would use

• % its existing equations to calculate releases from the plant and exposures due to these releases. The licensee stated that the LCOs and surveillance requirements involving the ODCM should be effective at the restart of the Cycle 11R outage when the ODCM software would be operational.

The meeting continued on August I with discussions on eouipment problems associated with the RETS. The equipment discussed were the Turbine Building sump monitor, liquid effluent discharge monitor, and Radioactive

_6 Gaseous Effluents Monitoring System (RAGEMS).

.The licensee stated that the Turbine Building sump has a corroded liner which will be replaced this Fall. The radiation monitor for monitoring discharges from the sump is onsite. This sump would affect proposed TS 4.6.I.1 and Table 3.15.I.c. The licensee is now sampling before dis-l charging water from the sump as would be required as a default option if l the radiation monitor was in place and inoperable. The licensee stated l thet the sump water has never needed to be sent to the liquid radwasta systen for processing and discharging this water from the station is part l of its present progran to not discharge radioactive liquid effluent frem the station. The licensee stated that the new liner would be in place and the sump monitor would be operational by January 1,1986.

, The liquid effluent or overboard discharge monitor is designed to monitor l processed liouid effluent from the radwaste system. This monitor has net been in service since 1981. The licensee has been evaluating the desien deficiencies of the discharge pipe and monitor since 1981, and has 1

concluded that it cannot monitor a representative sample of the liquid e# fluent in the pipe. When the licensee has discharged liquid effluents in the past, it has sampled the liquids before discharge which is the default condition if the monitor was being used and was inoperable; however, the licensee has not discharged liquid effluents since the restart frnm the Cycle 10R outare.

The licensee is considering withdrawing the monitor from the proposed RETS and relying only on sampling liquid wastes before discharge. The licensee stated that it estimates that it would cost $150,000 to replace the pipe and monitor. This nonitor affects proposed TS Table 3.15.1.a and existing TS 3.6.B.2. The NRR project manager stated that the licensee would have to subrit e revision to the proposed RETS to have the staff consider the licensee withdrawing the liquid radweste effluent line monitor from the RETS.

RAGEMS is the radioactive gaseous effluent monitoring system for the main 's "  ;

stack and the Turbine Building vents. It was originally designed in .

1977/1978 to meet Appendix I to 10 CFR Part 50. It was revised to meet post-accident sampling and nonitoring requirenents of NUREG-0737. This revision required hardware und software changes to the system. It was installed in 1982, and the licensee stated it has yet to work correctly.

The licensee has now decided to keep the normal effluent and post-accident iodine and particulate sampling and the post-accident noble gas monitoring portions of RAGEMS. There will be a new systen for nomal effluent noble pas monitoring. The equipment for the stack is onsite and has been partially installed. The connection has not been made for readouts in the Control Room. The licensee states that it will take about one year to have this new system operational. The equipment for the turbine building vents is not onsite but will also be installed and operational before the restart from the Cycle 11R outape.

The existing stack gaseous monitoring system does not have effluent flow measurfog equipment required by the proposed RETS. The licensee does not presently, and is not required to, monitor or sample the Turbine Building vents. Releases from the main stack include the Turbine Building venti-lation. The Turbine Building vents are ventilation discharges from certain individual rooms in the Turbine Building, lube oil bay and feed-water, and from the top of the building. The Turbine Euilding vents are in proposed RETS Table 3.1.5.?, item 3.

The licensee stated that it will have the normal effluent iodine and particulate sampling eouipment operational at the end of the Cycle 11R outage. The existing equirrent for this sampling will meet the proposed RETS

except for the flow measuring eouipnent which is required by RETS but is not installed. This equipnent is operational on the stack but not on the Turbine Bud ding vent because the software for the Turbine Building vents releases is not written.

The licensee agreed to review the proposed RETS submitted by its letter dated October 22, 1984, and mark up the RETS to show when each TS can be implemented. This will be sent to the NRR project manager by the first of September.

2.0 Status of Licensing Actions The status of all the incompleted licensing actions on Oyster Creek was discussed. The significant items discussed and actions proposed or taken are listed below:

- RETS has been discussed in Item 1.0 above.

Inservice Testing Program (TAC No. 11270): the licensee stated that the decision on the licensee's submittal is needed by October 1, 1985, for the licensee to plan for the Cycle 11R outage. The last 10-year period ended with the Cycle 10R outage.

The licensee agreed to withdraw its proposed TS change dated September 25, 1984, on combined leakage rate for containment penetrations and isolation valves and will submit a new proposed TS change for the 4 staff to review.

The licensee stated that its submittal on post-accident plant shielding and the security building will be submitted by September 15, 1985.

NRR Project Manager requested that the licensee address the following items in future reouests for changes to the TS:

1. when will the procedures be written to implerent the change;

2. when will the procedures be implemented or modifications be made; and

3. when should surveillance be effective after the TS change is approved ar.d issued by the staff and the justification for this.

The licensee agreed to have a meeting with the State of New Jersey and the staff to discuss the Appendix P TS.

The licensee requested that tha staff not approve TS 3.3.D.1.c and 3.3.D.2 proposed in the licersee's letter dated October 22, 1984 Based on the licensee's discussions with the staff on these proposed TS, the licensee is subritting new proposed TS on the rate of increase in the unidentified RCS leakage which the licensee states should be clearer.

t 3.0 Next Meetino lhe August Progress Review Veeting will be held at the licensee's head-quarters in Parsippany, New Jersey on September 18, 1985, 1M. k g ack N. Donohew, Jr., Project Manager Operating Reactors Branch 5 Division of Licensing

Enclosures:

1. List of Attendees

2. Licensee Handouts cc: D. Crutchfield J. Zwolinski

AUG 2 g L 3.0 Next Meetina The August Progress Review Peeting will be held at the licensee's head-quarters in Parsippany, New Jersey on September 18, 1985.

slueed by MLb L fack H. Donohew, Jr., Project fianager Operating Reactors Branch 5 Division of Licensing

Enclosures:

1. List of Attendees

2. Licensee Pandouts cc: D. Crutchfield J. Zwolinski DISTRIBilTION Docket NRC PDR Local PDR

_0RB #5 Reading JZwolinski JDonohew CJamerson OELD EJordan

BGrimes ACRS (10) i NRC Participants l

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Petyped by JBrandenburg 8/16/85.

D ORB #5 DL #5 DL:0RB#5 C erson pJDenchew:mn JZwolinski 8//4/85 8/Q/85 (, /g4/85 l

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cc:

G. F. Trowbridge, Esquire Resident Inspector Shaw, Pittman, Potts and Trowbridge c/o U.S. NRC 1800 M Street, N.W. Post Office Box 445 Washington, D.C. 20036 Forked River, New Jersey 08731 J.B. Liberman, Esquire Commissioner Bishop, Liberman, Cook, et al. New Jersey Department of Energy 1155 Avenue of the Americas 101 Commerce Street New York, New York 10036 Newark, New Jersey 07102 Eugene Fisher, Assistant Director Regional Administrator, Region I Division of Environmental Quality U.S. Nuclear Regulatory Commission Department of Environmental 631 Park Avenue Protection King of Prussia, Pennsylvania 19406 380 Scotch Road Trenton, New Jersey 08628 BWR Licensing Manager Mr. P. B. Fiedler GPU Nuclear Vice President and Director 100 Interpace Parkway Oyster Creek Nuclear Generating Parsippany, New Jersey 07054 Station Post Office Box 388 Deputy Attorney General Forked River, New Jersey 08731 State of New Jersey Department of Law and Public Safety 36 Fest State Street - CN 112 Trenton, New Jersey 08625 Hayor Lacey Township 818 West Lacey Road Forked River, New Jersey 08731 D. G. Holland Licensino Panacer Oyster Creek Nuclear Generating Station Post Office Box 388 Forked River, New Jersey 08731

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• Attachment 1 MEETINGS July 31 and Auoust 1, 1985

1. Station Site, July 31, 1985, RETS:

Name ---Affiliation J. Donohew NRC/NRR/DL P. Czaya GPUN**

D. Cafaro GPUN S. Molello GPUN

• S. Greco GPUN P. Schwartz GPUN J. Sullivan GPUN C. Halbfoster GPUN R. Stoudnour GPUN

'J.

Moon State of New Jersey *

2. Station Site, August 1,1985, RETS:

J. Donohew NRC/NRR/DL l J. Moon State of New Jersey *

- W. Duda GPUN i R. Lorenzo GPUN G. Sadauskae GPUN l , R. Stoudnour GPUN

• S. Greco GPUN M. Kapil GPUN P. Czaya GPUN M. Laggart GPUN l

3. Station Site, August 1,1985, Status of Station Licensing Actions: l l J. Donohew NRC/NRR/DL M. Laggart GPVN l J. Moon State of New Jersey *

• Bureau of Radiation Protection

• • GPUN = GPU Nuclear Corporation

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