ML20126E630

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Summary of 850422 & 23 Meetings W/Utils at Site & Gpu Nuclear Corporate Headquarters Re Status of post-accident Sampling Sys & Status of Station Licensing Actions & Issues Listed in Encl Agenda
ML20126E630
Person / Time
Site: Oyster Creek
Issue date: 05/30/1985
From: Donohew J
Office of Nuclear Reactor Regulation
To:
Office of Nuclear Reactor Regulation
Shared Package
ML20126E632 List:
References
LSO5-85-05-043, LSO5-85-5-43, NUDOCS 8506170158
Download: ML20126E630 (20)
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  1. o,, UNITED STATES

<p p, NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555

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  1. May 30,1985 k *.... #

Docket No.: 50-219 LS05-85-05-043 LICENSEES: GPU Nuclear Corporation Jersey Central Power and Light Company FACILITY: Oyster Creek Nuclear Generating Station

SUBJECT:

APRIL 22 AND 23, 1985 MEETINGS ON STATUS OF POST-ACCIDENT SAMPLING SYSTEM BEING OPERATIONAL AND MARCH 1985 PROGRESS REVIEW MEETING ON LICENSING ACTIONS On Monday, April 22, and Tuesday, April 23, 1985, meetings were held at Oyster Creek Station site (April 22) and at GPU Nuclear Corporate Head-quarters (April 23) with GPU Nuclear (the licensee) to discuss the follow-ing: status of the Post-Accident Sampling System being operational (April 22), status of station licensing actions (April 22 and 23) and other issues listed in the enclosed agenda for the meeting at the corporate head-quarters (April 23). Enclosure 1 is the list of the individuals attending the meetings. Enclosure 2 is the agenda for the meeting at the GPU Nuclear Corporate headquarters. Enclosure 3 is a copy of the material presented by the licensee at these meetings. The following is a summary of the signif-icant items discussed and the actions taken or proposed.

The original plan to have the meeting at the station site on April 23 and at the corporate headquarters on April 22 had to be revised on or about April 18, 1985. A change to the staff's original meeting notice was sent out on April 19, 1985 and the State of New Jersey, Bureau of Radiation Protection, was notified by phone on that date.

The staff visited the control room and the new Technical Support Center at the site on April 22, Mr. Zwolinski toured the training facilities and emergency offices located about the site.

1.0 Post-Accident Sampling System (PASS)

NRC Confirmatory Order dated June 17, 1983, confirmed the licensee's commitment to have the PASS fully operational within 6 months after restart from the Cycle 10 refueling outage. This date was April 29, 1985. The staff had several discussions on the PASS being fully operational by this date with the licensee beginning on March 27, 1985, when the containment isolation valve V-24-29 was determined to be inoperable /

B506170158 PDR 8505ADOCK 050 g 9 P

because of high leakage past its seat and had to be shut during power operation. The licensee believed that the plant would have to be shut down in April 1985, before April 29, 1985, for reasons other than to ensure the operability of the PASS and would be down for a sufficient duration to draw the required samples into PASS. The possibility of this happening disappeared on April 17, 1985 and the licensee decided to request an extension to the Confirmatory Order. This meeting was then set up for the staff to discuss the status of PASS with the licensee.

Subsequent to the TMI-2 incident, the need was recognized for PASS to determine the extent of core degradation following a severe reactor accident. Criteria for an acceptable sampling and analysis system was specified in NUREG-0737, Item II.B.3. The system should have the capability to obtain and quantitatively analyze reactor coolant and containment atmosphere samples during and following an accident in which there is core degradation. Materials to be analyzed and quantified include certain radionuclides that are indicators of severity of core damage (e.g., noble gases, isotopes of iodine and cesium, and nonvolatile isotopes), hydrogen in the containment atmosphere and total dissolved gases or hydrogen, baron, and chloride in reactor coolant samples. The staff's evaluation of the licensee's PASS was issued in the Safety Evaluation dated August 19, 1984 In the meeting, the licensee made a presentation on the PASS. This included the following: the capabilities of the PASS; the schedule for the implement-ation nf the PASS from the design to the purchase, installation, and now the testing of the installed system; the completed vendor testing of PASS and pictures of the PASS as installed at Oyster Creek including the front panel.

Enclosure 3 has the material handed out by the licensee at the meeting. Copies of the functional test procedure and supplemental test procedure for PASS were handed out but they are not included in Enclosure 3 because of their thickness.

The licensee stated that (1) all samples from PASS can be analyzed onsite and do not have to be sent offsite , (?) the operating procedures for PASS should be approved by April 22 and (3) the PASS meets the eleven criteria given in the staff's Safety Evaluation dated August 19, 1984, on PASS.

The remaining functional tests still to be done for PASS to be declared fully operational were identified by the licensee. These are on page 5 of the hand out, " Post Accident Sampling System (PASS) Program", in Enclosure 3. These are the following:

A) Take representative small and large volume samples from shutdown cooling system - need proper plant conditions B) Take representative small and large volume samples from a recirculation loop and liquid poison system - need V-24-29 repaired C) Take large volume dissolved gas sample from shutdown cooling system - I need proper plant conditions ,.

D) Take large volume dissolved gas sample frc:s a recirculation loop and liquid poison system - need V-24-29 repaired E) Analyze gas samples on gas chromatograph - this should be operational today F) Verify ability of sample coolers to cool sample - need V-24-29 re-paired to take hot sample The licensee stated valve V-24-29 cannot be opened because the valve was determined to be inoperable and station Technical Specifications require it to be shut during power operation. Therefore, the last functional tests still to be done on PASS (except E above) cannot be done unless the station shuts down so valve V-24-29 can be opened and samples can be drawn from the shutdown cooling system. The licensee stated that except for not being able to draw samples from certain systems the PASS is actually fully operational and, if there is an emergency which would require the use of PASS, the PASS would be able to obtain the required samples. The PASS was tested by the vendor.

The staff stated that other licensee's have requested extensions to the date when the PASS would be fully operational and that Technical Specifications on PASS do not require a plant to shut down if PASS is inoperable. The staff stated that, if the licensee is planning to request an extension to the date in the Confirmatory Order, it should do so immediately. This letter should also in-form the staff when the licensee will propose Technical Specifications on PASS.

The licensee, by letter dated April 22, 1985, requested an extension to the date in Confirmatory Order dated June 17, 1983, when PASS must be fully oper-ational. The staff, by a license amendment dated April 29, 1985, chan date when the NUREG-0737, Item II.B.3, Post-Accident Sampling System (ged thePAS required to be fully operational. This date will now be the next shutdown of known sufficient duration to (1) open valve V-24-29 and draw reactor coolant water samples from the Reactor Recirculation System and the Liquid Poison System and (2) draw a sample from the Shutdown Cooling System but no later than before the restart from the planned outage currently scheduled for October 1985 or the Cycle 11 Refueling Outage whichever is earlier. The amendment was approved by a telephone call from the NRC Oyster Creek Project Manager on April 29, 1985.

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2.0 Status of Licensing Actions The status of all the open licensing actions on Oyster Creek was discussed. No significant items were discussed and no actions were taken or proposed.

3.0 Meeting At Corporate Headquarters Enclosure 3 includes the licensee's agenda for the meeting at Corporate Headquarters on April 23, 1985. On procedures to implement the licensee's Technical Specification Change Requests (TSCR) the staff requested that the licensee address the following in the TSCR: (1) schedule to develop precedures to implement the TSCR, (2) if the licensee would use these procedures before staff approval of TSCR and (3) date the TSCR should become effective after staff approval. The licensee agreed to consider committing to this.

The staff and the licensee discussed delays in the staff receiving the licensee's submittals to close out open sections in the Oyster Creek Integrated Plant Safety Assessment Report. This was issued by the staff as a final report (NUREG-0822) on January 1983 as part of the staff's Systematic Evaluation Program. There are submittals on six issues which the staff has still not received. Dates for each submittal were given by the licensee.

As part of the discussion on prioritization, integrated schedule, plant improve-ments and NRC requirements, the licensee handed out a " draft" copy of the licensee's present look at the Cycle 11 refueling outage and the Fall 1985 outage. The Cycle 11 outage is presently scheduled for April 12, 1986. This handout is included in Enclosure 3 and is marked " draft".

The licensee is planning a request soon to NRC to defer certain NRC requirements. Deferment would be from the Cycle 11 refueling outage to the Cycle 12 refueling outage. The Cycle 12 outage is expected in 1988. The defer-ment would be based on the large amount of work to be completed in Cycle 11 and the large number of personnel that must be onsite to do the work.

The staff stated that the schedule date to complete its review of the licensee's requested exemptions to Appendix R, Fire Protection Program, will be changed. The new date will meet the deadline for the licensee to ccmplete its engineering for Cycle 11. This has been done by the staff.

The licensee stated that the April 12, 1985, date to shut down for Cycle 11 is a firm date. This date is based on the reactivity in the core. The plant should begin coastdown in power in January, 1986. Delaying the shutdown of the

, station to begin Cycle 11 may possibly result in derating the station when it comes out of Cycle 11.

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r 4.0 Next Meeting In the January 1985 Progress Review Meeting Summary dated February 22, 1985, I stated a meeting would be held at Oyster Creek on March 20, 1985.

This meeting was cancelled. The April Progress Review Meeting was held at NRC on May 14, 1985.

a . on w r, Project Manager Operating Reactors Branch 5 Division of Licensing

Enclosures:

1. List of Attendess
2. Agenda
3. Licensee Handouts i

cc: D. Crutchfield J. Zwolinski DISTRIBUTION:

Central File ORB #5 Reading CJamerson JDonohew JZwolinski p ,

O s CEB#5/DL ORB #5/DLQ JDc w/mac 41/JZwolinski CJamerson 05/ 85 l 05/yj/85 05/30 /85

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Mr. P. B. Fiedler Oyster Creek Nuclear Generating Station Oyster Creek Nuclear Generating Station 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 PJshop, 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 Division of Environmental Quality Nuclear Reoulatory Commission Department of Environmental Region I Office Protection 631 Park Avenue -

380 Scotch Road King of Prussia, Pennsylvania 19406 Trenton, New Jersey 08628 BWR Licensing Manager GPU Nuclear 100 Interpace Parkway Parsippany, New Jersey 07054 Deputy Attorney General State of New Jersey Department of Law and Public Safety 36 West State Street - CN 112 Trenton, New Jersey 08625 Mayor Lacey Township 818 West Lacey Road Forked River, New Jersey 08731 U.S. Environmental Protection Agency Region II Office ATTN: Regional Radiation Representative 26 Federal Plaza New York, New York 10007 D. G. Holland Licensing Manager Oyster Creek Nuclear Generating Station Post Office Box 388 Forked River, New Jersey 08731 9

Enclosure 1 MEETINGS April 22/23, 1985

1. Station Site, April 22, Post-Accident Sampling System:

Name Affilation J. Donohew NRC/NRR/DL J. Zwolinski NRC/NRR/DL M. Hober State of New Jersey

  • W. Popow GPUN**

W. Behrle GPUN P. Fiedler Director /0yster-Creek ,

J. Gulati GPUN W. Bateman NRC/ Resident inspector J. Wechselberger NRC/ Resident inspector E. Connor NRC/ Region I J. Tuohy Burns & Roe B. Hohman GPUN C. Halbfoster GPUN D. Holland GPUN W. Fitts GPUN J. Thorpe GPUN

2. Station Site, April 22, Status of Station Licensing Actions:

J. Donohew NRC/NRR/DL M. Laggart GPUN M. Hober State of New Jersey

3. GPUN Corporate Headquarters, April 23,:

J. Donohew NRC/NRR/DL J. Zwolinski NRC/NRR/DL M. Laggart GPUN J. Thorpe GPUN R. Wilson GPUN C. Tracey GPUN Keating GPUN Y. Nagai GPUN

  • Bureau of Radiation Protection
    • GPUN = GPU Nuclear Corporation

Enclosure 2 AGENDA FOR APRIL 23, 1985 MEETING GPU NUCLEAR HEADQUARTERS OYSTER CREEK STATION

1. Introduction of New ORB #5 Branch Chief.
2. Discussion on Process for Developing Procedures to Implement TS Changes and for Equipment becoming Operational.
3. Licensee's Prioritization of Work, Integrated Schedule and Impacts on Licensee's Resources.
4. Licensee's Late Submittals, How to Reduce this Delay.
5. Inferior TS change Applications.
6. Discussion on Relationship between Plant Improvements and NRC Requirement.
7. Status of Station Licensing Actions.

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Enclosure 3 Material Presented By Licensee At The April 23 and 24, 1985, Meetings At The Oyster Creek Site (April 22) And The Licensee's Corporate Head-quarter's (April 23)

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POST ACCIDENT SAMPLING SYSTEM (PASS)

THE PASS MODIFICATION PROVIDES THE PLANT WITH THE CAPABILITY TO OBTAIN LIQUID AND GAS SAMPLES FROM WITHIN THE PRIMARY CONTAINMENT FOR RADIOLOGICAL ANALYSIS IN ASSOCIATION WITH THE POSSIBLE LOCA EVENT (IE. SATISFYING NUREG 0737-II.B.3)

THE PASS SYSTEM IS DESIGNED TO OBTAIN REPRESENTATIVE LIQUID AND GAS SAMPLES FROM THE DRYWELL AND THE REACTOR VESSEL FOR RADIOLOGICAL ANALYSIS.

THE PASS SYSTEM INCLUDES THE FOLLOWING:

  • GE SAMPLE STATIO;-
  • CONTROL CABINETS
  • LIQUID CHILLER
  • DEMINERALIZED WATER TANK
  • RADIATICN MONITORS
  • FUME hot'D
  • CONTAINMENT AND SAMPLE ISOLATION VALVES
  • PIPING STATIONS

THE SAMPLE STATION IS LOCATED IN THE OFFICE BUILDING-NORTH END INSIDE THE OLD DESIGNATED COUNT ROOM ON ELEVATION 35 FOOT.

THE LIQUID SAMFLING UNIT IS DESIGNED TO OBTAIN A SMALL (0.1ML) AND LARGE (10ML) SAMPLE.

THE GAS SAMPLING UNIT IS DESIGNED TO OBTAIN A GAS SAMPLE (1/

ALSO CAPABLE OF COLLECTING IODINE AND/OR PARTICULATE SAMPLE:

THE SAMPLE STATION IS DESIGNED WITH LEAD SHIELDING TO LIMIT PERSONNEL EXPOSURE.

THE SAMPLE STATION IS VENTED TO THE REACTOR BUILDING.

THE LIQUID SAMPLER IS DESIGNED TO OBTAIN THE FOLLOWING SAMPLES:

THE GAS SAMPLER IS DESIGNED TO OBTAIN THE FOLLOWING SAMPLES:

  • DRYWELL ATMOSPHERE SAMPLE VIA A CONNECTION TO THE HYDROGEN MONOTORING SYSTEM.
  • DRYWELL ATMOSPHERE SAMPLE VIA A CONNECTION TO THE DRYWELL OXYGEN ANALYZER.
  • TORUS ATMOSPHERE SAMPLE VIA i CONNECTION TO THE TORUS OXYGEN ANALYZER

DOCUMENTS CODES, STANDARDS, REGULATIONS, ETC. FORM PART OF THE DESIG.

REQUIREMENTS:

  • RG 1.26, QUALITY GROUP CLASSIFICATION
  • RG 1.29, SEISMIC DESIGN CLASSIFICATION
  • RG 1.30, QUALITY ASSURANCE REQUIREMENTS
  • ANSI B 31.1, POWER PIPING
  • GENERAL ELECTRIC CO (NUCLEAR ENERGY) DESIGN SPEC

-PASS PIPING / INSTRUMENTATION DIAGRAM

-BWR EQUIPMENT ENVIRONMENT INTERFACE DATA

  • BURNS & ROE INC.-OCNGS SPECIFICATION

-DESIGN SPECIFICATION

-INSTALLATION SPECIFICATION

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  • OTHER ACTIVITIES PWS EQUIPMENT ACCESS (IE. CASK,ETC)

-OFF SITE ANALYTICAL SERVICES

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a POST ACCIDENT SAMPLING (PASS) TEST PROGRAM

1) TWO TYPES OF TESTING:

A) PERFORM MECHANICAL, ELECTRICAL, I&C CHECKOUT OF PASS STATION AND DEMONSTRATE ABILITY TO TAKE VARIOUS LIQUID AND GASEOUS SAMPLES (INCLUDING IODINE / PARTICULATE CARTRIDGE SAMPLES) -

PERFORMED BY SU/T GROUP USING CRAFT SUPPORT FOR HARDWARE CHECK AND PLANT CHEM TECHS TO TAKE SAMPLES.

B) ' CHECKOUT AND INITIALIZE ANALYZING EQUIPMENT AND DEMONSTRATE I

ABILITY TO ANALYZE ALL SAMPLES -

PERFORMED BY PLANT CHEMISTRY DEPT.

2) PASS STATION TESTING - 5 BROAD CATEGORIES:

A) VENDOR TESTING BY GE PRIOR TO SHIPMENT TO OYSTER CREEK B). SU/T GENERIC MECHANICAL, ELECTRICAL, I&C CHECKS PLUS M&C HYDRO / PRESSURE TEST OF PIPING / TUBING C) SU/T FUNCTIONAL TESTING OF EKIERNAL LIQUID & GAS SAMPLE VAL

  • AND CONTAINMENT ISOLATION-VALVES. TO VERIFY PROPER OPERATION, a

FLOW PATHS AND BYPASS OF ISOLATION SIGNAL CAPABILITY D) SU/T SUPPLEMENTAL TESTING:

- TO VERIFY CAPABILITY TO TAKE LARGE AND SMALL VOLUME LIQUID 1

-SAMPLES USING DEMIN WATER

- TO TAKE ALL GAS SAMPLES WITH FREON

- IODINE / PARTICULATE

- CARTRIDGE DRAWER OPERATION

- SYSTEM FLUSHING

- ABILITY TO BLOW COLLECTOR AND THOROUGH VERIFICATION OF ALL h INTERLOCKS PRIOR TO INTRODUCING RADI0 ACTIVE SAMPLES

E) SU/T FUNCTIONAL TEST TO DEMONSTRATE CAPABILITY TO TAKE SMALL AND LARGE VOLUME LIQUID SAMPLES FROM EACH LOCATION, CAS SAMPLES FROM EACH LOCATION AND PARTICULATE / IODINE CARTRIDGE SAMPLES FROM 23' ELEVATION IN DRYWELL.

ALSO DEMONSTRATE COOLING CAPABILITY OF COOLERS, ABILITY TO TAKE ,

LARGE VOLUME DISSOLVED GAS SAMPLES, ABILITY TO ADEQUATELY FLUSH SYSTEM AFTER SAMPLING.

3) VENDOR TESTING BY GE:

A) 15 MINUTE PRESSURE TEST OF LIQUID SUBASSEMBLY AT 1200 PSIG B) 15 MINUTE PNEUMATIC TEST OF GAS SUBASSEMBLY AT PRESSURES RANGING FROM 15 PSIG TO 100 PSIG ,

C) VERIFICATION OF ALL PAN 8L WIRING TERMINATIONS D) VERIFICATION OF ABILITY TO:

- BLOW COLLECTOR

- TAKE LIQUID SAMPLES FROM ALL SOURCES WITH DEMIN WATER

- TAKE GAS SAMPLES FROM ALL SOURCES WITH FREON

- TAKE DISSOLVED GAS FROM LARGE VOLUME SAMPLE USING FREON IN KRYPTON INJECTION SYSTEM (SINCE DELETED)

- TAKE IODINE / PARTICULATE SAMPLES USING FREON

- FLUSH PASS STATION FOLLOWING SAMPLING OPERATIONS

,0BTAIN CRITICAL VELOCITY FOR IODINE / PARTICULATE SAMPLE

- OBTAIN 2 1 GPM LIQUID SAMPLE FLOW IN THE BYPASS MODE

- OBTAIN 2 18 SCFH CAS FLOW IN THE CIRCULATE GAS MODE

- OPERATION OF VARIOUS PRE-EMPTIVE INTERLOCKS

4) SU/T GENERIC TESTS FOLLOWING FIELD INSTALLATION AND HYDRO / PNEUMATIC TESTING BY M&C:

A) MECRANICAL TESTING -

CHECK ALL VALVES FOR PROPER STROKE MONITOR PUMPS (P-601, 701, 702) OPERATION AND TAKE VIBRATION READINGS B) ELECTRICAL TESTING -

VERIFY CORRECT WIRE IDENTIFICATION, TERMINATION TIGHTNESS AND CORRECTNESS OF INTERNAL PANEL AND FIELD TERMINATIONS AGAINST WIRING DRAWINGS.

ALSO PERFORM POWER BREAKER TRIP TESTS C) I&C - ,

BENCH (AS PRACTICAL) AND LOOP CALIBRATE ALL INSTRUMENTS

5) SU/T FUNCTIONAL TESTING OF EXTERNAL VALVES:

A) VERIFY PROPER OPERATION AND FLOW PATH WITH DEMIN WATER FOR EXTERNAL LIQUID SAMPLE VALVES (V-40-6, 8, 12, 24) AS PRACTICAL B) VERIFY PROPER OPERATION AND FLOW PATH WITH 2N OR AIR FOR EXTERNAL GAS SAMPLE VALVES (V-40-14, 16, 20)

C) VERIFY CAPABILITY TO OPERATE AND BYPASS (DURING A CONTAINMENT ISOLATION SIGNAL) ALL VALVES REQUIRED FOR SAMPLING THAT NORMALLY CLOS,E ON A CONTAINMENT ISOLATION SIGNAL (V-38-9, 10, 16, 17, 22, 23, V-24-29, 30)

D) FUNCTIONAL TEST OF ADDITIONAL MISCELLANEOUS SAMPLING VALVES (V-40-2, 26, 35)

6) SUPPLEMENTAL TESTING TO VERIFY:

A) LIQUID SAMPLING CAPABILITY FROM ALL SOURCES USING DEMIN WATER (SMALL AhD LARGE VOLUME SAMPLES)

-d B) ABILITY TO TAKE DISSOLVED CAS SAMPLE C) PROPER OPERATION OF IODINE / PARTICULATE CARTRIDGE D) GAS SAMPLING CAPABILITY FROM ALL SOURCES USING FREON E) ABILITY TO BLOW COLLECTOR F) ABILITY TO FLUSH / PURGE SAMPLE PATH AFTER SAMPLING G) VERIFY PROPER VALVE ALIGNMENT / RELAY OPERATION IN EACH STEP ABOVE H) PERFORM CERTAIN NEGATIVE OR PRE-EMPTIVE CHECKS TO VERIFY THAT OPERATOR ERROR WILL NOT CAUSE SAMPLING PROBLEMS / SPILLS

7) SU/T FUNCTIONAL TESTING COMPLETED TO DATE:

A) BLOW COLLECTOR OPERATIONS - OK B) TAKE REPRESENTATIVE SMALL AND LARGE VOLUME SAMPLE FROM CORE SPRAY SYSTEM (3.5AMHO SAMPLE VS 3 AMHO ANALYZED) - OK C) TAKE REPRESENTATIVE GAS SAMPLES FROM:

TORUS - SAMPLES IN BALL PARK BUT 75' ELEVATION OF DRYWELL NEED GAS CHROMAT0 GRAPH l

23' ELEVATION OF DRYWELLJ OPERATIONAL FOR FINAL CHECK REACTOR BUILDING - OK D) TAKE REPRESENTATIVE IODINE / PARTICULATE SAMPLES FROM 23' ELEVATION DRYWELL - LOWER THAN PLANT SAMPLE BY W I 1/2-2

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8) SU/T FUNCTIONAL TESTING REMAINING:

A) TAKE REPRESENTATIVE SMALL AND LARGE VOLUME SAMPLES FROM SHUTDOWN COOLING - NEED PROPER PLANT CONDITIONS B) TAKE REPRESENTATIVE SMALL AND LARGE VOLUME SAMPLES FROM A RECIRC LOOP AND LIQUID POISON - NEED V-24-29 REPAIRED C) TAKE LARGE VOLUME DISSOLVED CAS SAMPLE FROM SHUTDOWN COOLING -

NEED PROPER PLANT CONDITIONS D) TAKE LARGE VOLUME DISSOLVED GAS SAMPLE FROM A RECIRC LOOP AND LIQUID POISON - NEED V-24-29 REPAIRED E) ANALYZE GAS SAMPLES ON GAS CHROMATOGRAPH - GC SHOULD BE OPERATIONAL TODAY F) VERIFY ABILITY OF SAMPLE COOLERS TO COOL SAMPLE - NEED V-24-29 REPAIRED TO TAKE HOT SAMPLE

9) SOME ITEMS THAT WE CANNOT VERIFY WITH CURRENT ACTIVITY LEVELS:

A) DEMIN WATER FLUSH TO BRING DOWN RADIATION LEVELS PER RI-665 B) N2 PURGE TO BRING DOWN RADIATION LEVELS PER RI-704

10) ITEMS THAT ARE STILL BEING RESOLVED BY ENGINEERING:

A) OF THE 3 IODINE / PARTICULATE SAMPLES TAKEN TO DATE; ONE WAS DRY, ONE CONTAINED 10 ml LIQUID, ONE CONTAINED 3 1/2 ml LIQUID.

WHEN CONPARED WITH PLANT SAMPLES, 10 ml LIQUID SAMPLES WAS OFF BY FACTOR OF 10-100, 3 1/2 ml LIQUID SAMPLE WAS OF1 BY FACTOR OF 4 2, AND DRY SAMPLES WAS OFF BY FACTOR OF 1 1/2.

B) HEAT *.AACING TEMPERATURE ON DRYWELL GAS SAMPLE LINE IS,c(230*F VS GE SPECIFICATION OF 250*F. IS 230*F ACCEPTABLE FOR OYSTER CREEK?

WILLIAM BEHRLE MANAGER - STARTUP AND TEST APRIL 22, 1985

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