ML20199D922
| ML20199D922 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 03/14/1986 |
| From: | Donohew J Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8603240421 | |
| Download: ML20199D922 (31) | |
Text
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o UNITED STATES
! N- NUCLEAR REGULATORY COMMISSION
$ WASHINGTON, D. C. 20555 March 14,1986 Docket No. 50-219' 4
LICENSEES: GPU Nuclear Corporation Jersey Central Power and Light Company FACILITY: Oyster Creek Nuclear Generating Station
SUBJECT:
JANUARY 1986 PROGRESS REVIEW MEETING ON LICENSING ACTIONS On Thursday, February 20,-1986, at the Oyster Creek plant site at Forked River, New Jersey, a meeting was held with GPU Nuclear (the licenseei to discuss the status of station licensing actions.
Attachment 1 is the list of the individuals that attended the meeting. The following is a summary of the significant items discussed and the actions taken or proposed. References will be made to Cycle 11 Refuelino (Cycle 11R) outage which is scheduled to begin April 1986.
Attachment 2 is a marked up copy of the staff's Licensing Actions Report (LAR) dated December P4, 1985 for Oyster Creek. The markuo, to update the LAR, resulted from the discussion on each item in this meeting.. The status of each item is given in the column "SCT0ADTE" on the right-hand side of the LAR sheet. The status in that column is the following: "01" means licensee, "02" means staff's reviewer, "03" j means staff's Project Manager, "04" means action completed and "05"
- means staff's project manager has licensing action in concurrence.
Attachment 3 is future licensee Technical Specification Change Requests (TSCR). Attachment 4 is a listing of high priority licensing actions. Attachment 5 is the overall status 'of licensino actions.
Attachment 6 is information given the staff's project manager by the licensee. Attachment 7 is information and a request for information given the licensee by the staff's project manager.
1.0 Answer For Request For Information In December 1985 Proaress l Review Meeting i
The :ensee stated on page 4 of its letter dated September 24, 1985, lat deletion of the TS requirement on the drywell-to-torus differential pressure has eliminated the need to open the large l containment vent and purge valves following the vacuum breaker t operability test. The staff requested the reduction in the amount of time that the licensee would be operatinq with the larae containment valves open because of the deletion of the above TS requirement. The licensee stated that there is actually no reduction because there is another surveillance test on the same torus /drywell vacuum breakers which was done during the above mentioned test. The licensee is looking into doina the second test without having to open the large containment valves.
8603240421 860314 PDR ADOCK 05000219 P PDR
2.0 Future Licensee Technical-Specification Change Reauests (TSCR)
In the December 1985 Progress Review Meeting (Summary dated February 12,1986), the licensee listed 4 TSCR which it was planning to submit soon. These-4 TSCRs are in Attachment 3. The licensee dates to submit these 4 TSCR are the followina:
(a) Excess Flow Check Valves 3/31/86 (b) Diesel Generator Batteries submitted (c) Diesel Generator Loadina 3/15/86 (d) Rod Worth Minimizer 4/12/86 3.0 Future Meetinas Requested By Licensee (1) The licensee requested a meeting on the staff's criteria for TMI Items II.F.1.1 and II.F.1.? at Oyster Creek because of problems in its Radioloaical Gaseous Effluent Monitoring System (RAGEMS) meeting the criteria in NijREG-0737. The licensee reauested the involvement of the Region I-inspectors who did inspection 86-02. The staff agreed to the meetina. (Meeting at NRC Headquarters Bethesda, Maryland: April 2, 1986).
(2) The licensee reauested a meeting on the status of its Expanded Safety System Facility for Wednesday, March 26, 1986. The staff agreed. (Meeting at NRC Headquarters:
March 26, 1986).
(3) The licensee requested a meeting in March on the staff's
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request for information in the letter dated January 27, 1986. The licensee will explain when the containment purge and vent valves must'be open for surveillance tests during startup while the reactor is below its operating pressure.
The staff agreed. (Meeting at NRC Headquarters: March 20, 1986).
(4) The licensee requested a meeting in March on its request to not uparade its . nitrogen purge / vent system. This is in its letter dated September 26, 1985. The licensee explained that the drywell will stay below the flammability limit for 30 days after the design basis loss-of-coolant-accident (LOCA) without adding nitrogen or purging the containment.
There are three levels of defense for combustible pas control during a LOCA at Oyster Creek: (1) a drywell, limited by the desian of the torus, to 35 osia, (2) the drywell is inerted to 4% oxygen, and (3) the drywell does not have to be purged or to have nitrogen added. (Meeting at NRC Headquarters: -
March 27, 1986).
The staff project manager requested that the license provide, at the requested meeting, curves versus time for 30 days after the LOCA of the following: oxygen generation and percentage, hydrogen generation and percentaae, nitrogen addition and pressure in the drywell. The hydrogen and oxygen generation shall be for RG 1.7 and the BWROG source term and the containment leakage shall be for 0.5%/ day and no leakage.
4.0 Generic Letter (GL) 86-02 GL 86-02, Technical Resolution of Generic Issue B-19,~ Thermal Hydraulic Stability, was issued January 23, 1986, to all licensees of operating BWRs includina the licensee for Oyster Creek. It stated that BWR licensees must examine future core reloads to assure that thev are typical of previously evaluated cores which have an acceptable stability margin. BWRs such as Oyster Creek with its fuel design and operatina restrictions should.have sufficient margin. The project manaaer requested if the present core is typical of previously evaluated cores which have an acceptable stability margin.
5.0 10 CFR 50.92 Sholly Process 10 CFR 50.92 specifies three factors that a licensee must address to determine that a TSCR is not a significant hazard consideration.
To meet 50.92, the staff project manager stated that the licensee must address each factor in its TSCR and provide the basis for meeting each factor. The project manager recommended that the licensee use a similar format to that handed out in the January 30, 1986, ccunterparts session. The summary of this session is dated Februa ry - 10, 1986.
The staff project manager also requested that the licensee provide the following information with each submittal requesting a review from the staff as an TSCR:
(1) When the licensee needs to have the review completed and why, (2) The priority of this review with respect to all Oyster Creek licensina issues before the staff, (3) When, if applicable, the procedures to implement the action will be written, (4) When, if applicable, the action will be implemented after the staff-completes its review, and (5) What sections of the Oyster Creek FSAR apply to this issue.
.4_
The staff project manager states that this information is needed by the staff to properly manage the workload in the Division of BWR Licensing including the issues involving Oyster Creek. If this information is not provided, it will be requested by the staff.
6.0 NRC Staff Requests The staff project manager requested an up-to-date controlled copy of the Oyster Creek Emergency Operating Procedures (EOP1, Quality Assurance Manual and prints.
7.0 Snubber Technical Soecifications (TSCR) (TACs 08439,084401 The licensee and the staff project manager discussed this TSCR on hydraulic and mechanical snubbers with the Oyster Creek resident inspector, W. Bateman. The licensee proposed testing of snubbers Der operatina cycle versus per refueling outage. Also the licensee proposed removing a snubber, making it inoperable, for testing. The NRC Reaion has not completed its evaluation of the licensee's TSCP. Existing TS have the snubbers tested in a refueling outage but snubbers are also needed in a refueling outage.
8.0 Torus Modifications For Cycle 11R Outage and Operating Cycle 11 The licensee requested in a letter dated July 26, 1985, the deferment of certain torus attached oipino modifications from Cycle 11R outage to operatina Cycle 11. The listina is in Attachment 6.
9.0 Staff Ouestions for Suppression Pool Thermal Mixina Mooifications (TAC 60152 and 60153)
The licensee and staff project manager discussed the staff's cuestions on the suppression pool thermal mixing modification in Attachment 7. The licensee has requested cancellation of the modifica' .ons in its letter dated October 31, 1985. The staff's
< questions were read to the licensee on Tuesday, February 18, 1986. The licensee's answers to the questions in Attachment /
are the following:
l l
l (1) The suppression pool temperature limits in the TS will remain the same because of NPSH for the core spray pumps.
l (2), (3) and (4) The licensee does not know the answers to these questions because these modifications were not related to l
NPSH for the core spray pumps. These modifications were l
proposed to deal with unstable condensation of steam blown
! down from the electro-maanetic relief valves (EMRV). The l calculations to answer the questions are detailed, require j modeling and would take at least 6 months to complete.
I The licensee explained that the two modifications are (1) adding temoerature monitoring in the vicinity of the two EMRV discharge headers in the torus and (2) rerouting a containment spray dynamic test return line. They are part of the torus attached piping modifications in the licensee's letter dated June 29, 1981. The purpose of the modifications is the following:
(1) To give the control room operators indications that the temperature of the water in the vicinity of the EMRV headers is reaching the point where unstable condensation would occur and result ia dynamic loads on the suppression pool shell during blowdown from a stuck open EMRV. This would read out in the control room.
(2) The operators would know, by the local pool water temperature, that they had a stuck open EMRV. In Germany, a stuck open EMPV with a straight open header resulted in unstable condensation of steam in the pool and localized dynamic loading. There was rocking of.the torus and local damage.
The work by General Electric in NED0-30837 showed that unstable steam condensation is not a concern when quencher devices are used on EMRV discharge pipina as exists at Oyster Creek.
(3) The test line is used for testing the operability of Containment Spray. Presently it goes into a torus /drywell vacuum breaker and drains into the torus suppression pool. The rerouting was to allow means to cause some recirculation in the pool to aid in thermal mixing in the vicinity of the EMRV discharge headers and lower local pool temperatures. There was no safety problem with the test line in its present design and location. The new design would be used, in conjunction with the-temperature monitoring and knowledge with the operators that they were at the temp-erature for the onset. of unstable condensation, to (1) cause better thermal mixing in the vicinity of the headers and (2) prevent unstable condensation conditions.
The staff Pro.iect Manaaer stated that the temperature monitoring in itself would not prevent any unstable conditions and there are other safety grade and redundant indications to identify when an EMRV is stuck open. These indications are in the TS. There is also torus bulk water temperature indication in the control room.
The orerators have E0P addressing the situation of a stuck open EMRV. This was verified and discussed briefly with the operators on February 21, 1986, in a tour of the control room. The location for and size of the reroutea test line does not indicate it would be effective in causing torus pool circulation in the vicinity of the headers.
The staff Project Manager stated that the licensee did not nave to provide any further answers to the staff's cuestions in Attachment 7.
10.0 GPUN BWR Licensing Manaaer Visit NRR/NRC The GPUN BWR Licensing Manager for Oyster' Creek was requested to choose a one week period to spend at NRR headquarters in
- Bethesda, Maryland. This is for the licensing manager to better understand the procedures that'the staff pro.iect manager must follow. This is the third licensee licensing manager for a plant in RWR Project Directorate #1 (RWD#1) in NRR to be invited.
4
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11.0 Staff's Requests For Additional Information A list by date and subject of the staff's requests for additional information from the licensee is given in Attachment 7 12.0 Updated NRR Licensino Action Report (LAR) Dated 02/93/86 Attachment 2 has the updated LAR for Oyster Creek. The updating was done during the discussion on each licensing action in this meeting. The licensing actions are listed by TAC number (left-hand column of LAR).
i
- - 13.0 Hioh Priority Licensing Actions Attachment 3 is a list of the high priority licensing actions.-
These were taken from the overall list of licensing actions in -
- Attachment 2.
i 14.0 Overall Status of Licensing Actions Attachment 4 is the overall status of licensing actions.
l 15.0 General Housekeepino The staff project manager had a tour of the control room on
. Friday, February 21, 1986. .The control room and the -
- administration building were clean and neat.
f 16.0 Reactor Water level Instrumentation Two RE05 blind switches were found on Thursday, February 20, 1986, to have a significant non-conservative drift in their' setpoints. All the RE05/RE02 blind switches were tested as part of the monthly TS surveillance tests. The two RE05 switches were recalibrated and checked for repeatability and returned to service with the licensee's new test discussed in the January 23, t 1986, meeting summary dated February 24, 1986.
These Static Ring switches have only a travel of 0.018 inch and
. respond to only a band of 5-10 inches of water differential
' pressure. The switch has an internal hiah tech plastic diaphraam (polymide) with an inner steel disc. In the active pressure
- band, the steel disc moves off the back seat. A pin in the disc pushes into a hole in the opposite face and moves a cam.
MAR 141986
_7, All RE05/RE02 are tested each month and only the RE05 have had drift problems. These switches were installed in the Cycle 10M outage in October / November 1985. These switches were tested at low pressure in November and December and at operating pressure Jin January and February. The inoperability of an RE05 in January is discussed in the January 23, 1986, meeting summary dated February 24, 1986. This inoperable REOS was replaced.
The manufacturer has taken the inoperable RE05 apart and found no indication of its problem and no corrosion. The manufacturer tested the switch later at its facility and found no problems.
A similar switch is used at Oyster Creek for drywell pressure. It has been in service for 2 years without having to be recalibrated.
Two other plants are having drift problems similar to Oyster Creek with these switches in the same service.
17.0 Mark I Drywell Vacuum Breakers, Generic Letter 83-08 (TAC 57161)
The licensee is reviewing an MPR Associates Report on vacuum breaker chugging. The licensee must consider the probability and consequences of resonance chugging because the breakers do not meet the Mark I containment.for this unlikely condition. The licensee' stated.that its submittal will be sent by .
This was discussed with D. Holland and J. Rogers on Friday, February 21, 1986.
18.0 Next Meeting The February 1986 Progress Review Meeting is expected to be held at the NRR Headquarters in Beth a, Maryland on March 26, 1986, i
NN. Do W, Project Manager i
BWR Project Di ctorate #1 Division of BWR Licensing Attachments:
- 1. List of Attendees
- 2. Staff's Updated LAR
- 3. Future Licensee TSCR
- 4. High Priority Licensing Actions
- 5. Overall Status of Licensing Actions
- 6. Information From Licensee
- 7. Information and Request for Information From Staff cc: R. Bernero W. Hodges
, R. Houston L. Hulman i J. Zwolinski M. Srinivasan j G. Lainas D. Vassallo C. Grimes B.D. Liaw DISTRIBUTION
- f. Docket File m BWD#1 Reading CJamerson BGrimes 0C Service List i NRC PDR~" JZwolinski OELD ACRS (10) i local PDR JDonohew EJordan OC File DBL:PD#
ew:tm JZwolinski 3 $ 86 1 /8/86
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All RE05/RE02 are tested each month and only the RE05 have had drift problems. These switches were installed in the Cycle 10M outage in October / November 1985. These switches were tested at low pressure in November and December and at operating pressure in January and February. .The inoperability of an RE05 in January is discussed in the January 23, 1986, meeting summary dated February 24, 1986. This inoperable RE05 was replaced.
The manufacturer has taken the inoperable RE05 apart and found no indication of its problea and no corrosion. The manufacturer tested the switch later at its facility and found no problems.
A similar switch is used at Oyster Creek for drywell pressure. It has been in service for 2 years without having to be recalibrated.
Two other plants are having drift problems similar to Oyster Creek with these switches in the same service.
17.0 Mark I Drywell Vacuum Breakers, Generic Letter 83-G8 (TAC 57161)
The licensee is reviewing an MPR Associates Report on vacuum breaker chugging. The licensee must consider the probability and consequences of resonance chugging because the breakers do not meet the Mark I containment criteria for this unlikely condition.
This was discussed with D. Holland and J. Rogers on Friday, February 21, 1986.
i 18.0 Next Meeting The February 1986 Progress Review Meeting is expected to be held at the NRR Headquarters in Bethesda, Maryland on March 26, 1986.
N k N. Donohew, Proj :t Manager jBWRPro.iectDirectorate#1 V Division of BWR Licensing Attachments:
- 1. List of Attendees l 2. Staff's Updated LAR
- 3. Future Licensee TSCR
- 4. High Priority Licensing Actions
- 5. Overall Status of Licensing Actions
- 6. Information From Licensee
- 7. Information and Request for Information From Staff cc: R. Bernero W. Hodges R. Houston G. Hulman J. Zwolinski M. Srinivasan G. Lainas D. Vassallo B.D. Liaw C. Grimes
e cc:
Ernest L. Blake , Jr. Resident Inspector Shaw, Pittman, Potts and Trowbridae 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 Enerav 1155 Avenue of the Americas 101 Conmerce Street New York, New York 10036 Newark, New Jersey 07102 Eugene Fisher, Assistant Director Regional Administrator, Reaion 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 08678 BWR Licensing Manager P. R. Fiedler GPU Nuclear Vice President & Director 100 Interoace Parkway Oyster Creek Nuclear Generatina Parsippany, New Jersey 07054 Station Post Office Box 388 Deouty Attorney General Forked River, New Jersey 08731 State of New Jersey Department of Law and Public Safety 36 West State Street - CN 112 Trenton, New Jersey 08625 Mayor
. Lacey Township l 818 West Lacey Road Forked River, New Jersev 08731 D. G. Holland Licensing Manaaer Oyster Creek Nuclear Generatina Station
! Post Office Box 388 Forked F.iver, New Jersey 08731 I
Attachment 1 JANUARY 1986 PROGRESS REVIEW MEETING January 22, 1986 Name Affiliation P.'Czava GPUN#
R. Green NJRRP*
J. Donohew NRC/NRR/DRL M. Laqqart GPUN D. Holland GPUN W. Bateman NRC/ Region 1 Y
I
- State of New Jersev Bureau of Radiation Protection
- GPU Nuclear Corporation s
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-(HEADQUARTERS)
FACILITYs OYSTER CREEK 1 SC 7 To gg MULTI Y P RAI
$ RESPONSE SE INPUT LIC ACT AD '
TAC PLANT INIT P NOTICE R REV IER DATE DATE DATE COP 91ENTS , IE RAIE E EXPIRES 1 AftQH REVIENER RAI DATE DATE PLUMBER ACTION g3 (CONTINUATION) 3 c:nr3 ACTIVE ACTIONS NNNN 3 ACTION M52863 ITENs OYSTER CREEK 1 - ITEM 2.1 - EQUIPMENT CLASSIFICATION04/05/85 B-77 11/01/83 L BND1 DON 0 HEN AND VENDOR INTERFACE - RTS COMPONENTS 10/23/85C 11/30/86T 02 PAEI LASHER 10/30/86 ACTION ITEM: OYSTER CREEK 1 - ITEMS 3.1.1 8 3.1.2 - POST MAINTENANCE TESTING PROCEDURES / VENDOR RECOMMENDATIONS - RTS COMPONENTS 03/31/86T REGION I 02 M52944 3-78 11/01/83 L BND1 DON 0 HEN REG 1 HAVERKAMP 02/28/86 REG 1 JOHNSON g 02/28/86 g y -
RE01 SCHUMACHER g ACTION ITEM OYSTER CREEK 1-ITEM 3.1.3 -POST-MAINT TESTING-CHANGES TO TECH SPECS-RTS 02 j M53025 B-79 11/01/83 A BND1 DON 0 HEN 84/05/85 10/23/85C COMPONENTS 07/30/86T s PAEI LASHER 06/30/86 <-
ACTION ITEMS OYSTER CREEK 1 - ITEM 1.2 - POST TRIP REVIEN-DATA AND INFORMATION CAPABILITY 05/31/867 02 r M53615 3-85 11/01/84 L BND1 DON 0 HEN PAEI KRAMER 03/15/86.
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M53698 B-86 11/01/84 L BND1 DONONEN g PAEI LASHER 12/30/86 ACTION ITEM: OYSTER CREEK 1- ITEMS 3.2.1 8 3.2.2 - POST-MAINT TESTING PROCEDURES AND VENDOR REC03/31/86T BND1 DONOMEN 099tENDATIONS - ALL SR 02 COMP g g M53781 3-87 11/01/84 L RE01 HAVERKAMP
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/30/86T 02 B-88 11/01/84 A BND1 DON 0 HEN M53864 PAEI LASHER 06/30/86 g .g y
" ACTION ITEM: OYSTER CREEK 1 - ITEMS 4.5.2BND1 8 4.5.3 - REACTOR TRIP DONOHEN SYSTEM10/23/85C 04/05/85C FUNCTIONAL ~ TESTING - ALTERNATIVES K/30/86T 8 TEST INTERVALS 02 M54008 B-93 11/01/84 L g
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INF0RMAT.ON TRACKING SY$ TEM PA.. NO.8 44 R-1208473-e01 REOULAT0RY O DIVISION OF LICENSING RUN DATE: 02/05/86 -
LICENSING ACTIONS REPORT '
(HEAD 9UARTERS)
O FACILITY: OYSTER CREEK 1 SC T TO r5 Y P RAI
'gg MULTI RESPONSE SE INPUT LIC ACT AD TAC PLANT INIT P NOTICE R REV DATE TER DATE DATE DATE , COMMENTS IE j NUMBER ACTION B&l( g EXPIRES 1 DRGH REVIEMER RAI DATE (CONTINUATION) r)
() En=3 ACTIVE ACTIONS Muum
) ACTIDM ITEMS OYSTEk CREEK 1 - ITEM 4.5.1 BND1 DON -0 HEN REACTOR SYSTEM08/09/85C FUNCTIONAL TESTING 05/31/86T
- DIVERSE TRIP REGFEATURES I 02 5-92
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[3 i ACTION ITEM: OYSTER CREEK 1 - I.D.1.2 DETAILED CONTROL ROOM DESIGN REVIEN 84/08/85C F-71 10/22/84 PSD6 NICOLARAS
SUMMARY
REPORT 05/28/85- F-7104/05/85X 02/28/86T 10/09/85 M 95 TO.
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ACTION ITEM: OYSTER CREEK - LICENSEE'S PROPOSED CHANGES TO THE APPROVED ALTERNATE SAFE SHUTDONN y^ '?
'2f/f6TMIGH PRIOR 95 10/09/85C BHD1 DON 0 HEN
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(} PAPS GOEL 07/11/85C g ACTION ITEMS OYSTER CREEK - EXEN TIONS TO APPENDIX R - FIRE PROTECTIDM PROGRAM 10/09/85C 08/28/85C _2.f ?' y'"/I
' 'h. "1"NION PRIOR t M56786 01/22/85 PDPE KUBICKI ..
ITY BND1 DONOMEM ACTION ITENs OYSTER CREEK - REMOTE MANUAL bALVES (VI-4)
BND1 DONOHEN 08/27/85C 02/28/86T IPSAR 4.22 82 l M56951 10/01/82 .2 PBIA MCKENNA CD iC) .
ACTYONITEM8 OYSTER CREEK 1 - MARK 1 DRYNELL VACUUM BREAKERS, LICENSEE RESPONSE TO OENERIC LETTER 85-08 04/30/86T RAI et
,,M57161 BND1 DONOMEN 04/11/85 02/28/86 D-20 05/20/85 08/23/85X gp BND2 LONG gy BHER SHAM 4
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- OYSTER CREEK - EXTENSION TO 10CFR50.44(C)(3)(II)(B) - TMI ITEM BND1 DON 0 HEN II.E.4.1 08/14/85C 05/15/85T SEE M54018 03 M57758 12/24/81
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' DIVISION OF LICENSING RUM DATES 02/03/86 LICENSING ACTIONS REPORT (HEAD 9UARTERS)
O.
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) MULTI RESPONSE SE INPUT LIC ACT AD TAC PLANT INIT. P 50T?.CE R REV RAI DATE DATE TER DATE DATE DATE CDMMENTS IE MUMBER ACTION DAlg g ExFIRES 1 DRQH REVIEMER "
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IN SEP REVIEW 66 05/15/86T 2ND SET CD 01 F g
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ACTION ITEM: OYSTER CREEK 1 - 10 CFR 50.62 OPERATING PEPE KENDALL REACTOR REVIENS 19/04/85C 06/30/86T ATHS GA RE 82 M59122 4-20 06/28/84 PARS KARSCH 11/01/85X SPONSE Q j PAEI MAUCK BHDI DON 0 HEN NOl]'8[pf O2 ACTION ITEM: OYSTER CREEK - EXEMPTION OF 07/23/85 19CFR50.44(C)(3)(III) - ISOLATION BND1 DONOMEN N CONDENSER VENT ? ! ' ' 1' _ 7 -- AF M59342 BNRS HODGES og, f,gg h3/01/8&h TO CYCLE 12R ACTION ITEM OYSTER CREEK - DEFERMENT OF BND1 NRC DON REGUIRED MODIFICATIONS 11/20/85 FROM m CYC =C:^ ^T'- NIGH PRIOR 81 M59400 97/26/85 0 HEW - .,
8 A 11/29/850 .
03 I h e6/15/86T 01 O ACTION M59663 ITEM 8 OYSTER CREEK - EXPANDED SAFETY 03/11/85 SYSTEM FACILITY STATUS BND1 DON 0 HEW 01/22/86 PAEB BALLARD N /00 T O2.
- ACTION ITEM: OYSTER CREEK - SCOPE CHANGE FOR RECIRCULATION LOOP INTERLOCK, M59758 09/19/85 BHD1 DON 0 HEN II.K.3.19
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LICENSING ACTIONS REPORT
( H EA DQU A.'T FRS )
FACILITY: OYSTER CREEK 1 SC T TO A MULTI Y P RAI q INIT P NOTICE R REV RESPONSE SE INPUT LIC ACT AD TAC PLANT TER DATE DATE DATE C0f9 TENTS IE g EXPIRES 1 DRGH REVIEHER RAI DATE DATE NUMBER ACTION DMZ ,
g c =u ACTIVE ACTIONS NNNN (CONTINUATION) n ACTION ITEM: OYSTER CREEK - MAIN SECURITY SUILDINO POST ACCIDENT SHIELDINO 11.8.2 09/09/85 BWD1 DON 0 HEN 05/30/86T RAGEMS/REO
" 02 m 3 M59770 RE01 JOHMSON 04/30/86 j .I.' ISSUES
- J_ n am 'O-n .
Q ACTIONM59828 ITEMS OYSTER CREEK - CANCELLATION OF VEMi AND 12/06/85X 04/12/86T 01 O PURGE VALVES REPLACEMENT 09/24/85 SORI ELTAMILA 03/07/86 BHDI DON 0 HEN PSD0 HRIGHT n
Q BMEB LOMBARDO 1f ,g , s ACTION ITEMS OYSTER CREEK - CANCELLATION OF UPORADE OF MITR00EN VENT AND PURGE SYSTEM 12/06/85X 03/15/86T ~T{Arvi 82 O 09/24/85 SORI ELTAMILA Q M59829 BND1 DON 0 HEN BNPS HULMAN Of/28/84X BHPS HEARN Na2/15/86u g
O ACTION ITEMS OYSTER CREEK - CANCELLATION OF MODIFICATION TO INSTALL PRESSURE RELIEF IN PUROE AND VENT03/f7/86T EXMAUST DUCT 09/24/85 BWD1 DONOMEN M59830 BNPS HULMAN Sf/28/86X o O PBR$ KAPO 02/15/86 BNPS HEARN od iET/84T
.O ACTION ITEMS OYSTER CREEK - REv!SE OPERABILITY OFNLON-LON REACTOR g MATER LEVEL INSTRUMENTATIONMFOR REACTOR C VESSE ISOLATIO 1
M59935 10/11/85 01/18/86- gH N
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ACTION ITEM: OYSTER CREEK - CANCEL MODIFICATION TO PROVIDE SUPPRESSION POOL THERMAL MIXINO 03/17/86T 02
~M60152 10/31/85 BMDI DON 0 HEM g g DNPS MITT ACTION ITEM OYSTER CREEK - CANCEL MODIFICATIONS TO PROVIDE SUPPRESSION POOL TEMPERATURE MONITORINO 03/17/84T 02 g 10/31/85 BND1 DONOMEN g M60153 BNPS HITT
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M.
FACILITY OYSTER CREEK 1 SC T
. RESPONSE SE INPUT LIC ACT TAC PLANT INIT P NOTICE R REV BATE TER DATE BATE BATE C1NW1EMTS 11 NUMBER ACTION B&II E EXPIRES I ARGH REVIEMER RAI.DATE g3
, u=23 ACTIVE ACTIONS NNNN (CONTINUATION)
ACTION ITEM 8 OYSTER CREEK - COMPLY MITN LICENSED REACTOR OPERATORS STAFFING 11/07/85 01/18/86 BND1 DON 0 HEN 02/28/46 RE9UIREMENTS IN 10CFR50.54(M)(2) 04/30/867 NEN SUSMIT Of g ;
3 M60155 TAL ,-
ACTION ITEM 8 SYSTER CREEK - MINIMUM VOLUME IN DIESEL DEMERATOR STAND 0Y FUEL TANK TECHNICAL SPECIFICATION " /0"/;;7 CNANGE F3 i; 3
M60156 11/07/45 01/18/86 BND1 DON 0 HEM
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3 ACTION ITEM: OYSTER CREEK - LATTICE PHYSICS RELOAD TOPICAL REPORT FOR CYCLE !! 07/30/84T 02 M60339 11/25/85 DND1 DONOMEN s.
a 301 SCMEBULED ACTIONS u ACTION ITEM 8 SYSTER CREEK - POST ACCIDENT SAMPLING SYSTEM TECNNICAL SPECIFICATIONS 09/28/85 BNB1 DONOMEN 01/14/84C af C, 04
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M59281 06/14/85 v
ACTION ITEMS OYSTER CREEK - BIESEL DENERATOR TESTING INFORMATION M60554 01/17/86 DNB1 DONOMEN ng h Osb U
CCI COffLETED ACTIONS NNw ACTION ITEM: SYSTER CREEK - LONG TERM REVIEN CONTAINNENT PUR0E AND VENT (B-24) 89/24/85C 04/25/84C 01/21/84C NION PRI F 04 M42613 B-24 11/29/78 L 1 PAPS SHAPAKER 12/21/84X OR CYC IIR -
P900 WRIGHT 01/2f/86C BNB1 DONOMEN y !;
PAD 1 FAIRTILE 04/25/84C j
" ACTION ITEM 8 SYSTER CREEK - MASONRY MALL DESION. RESPONSE TO IE BULLETIN '04/14/85C 2 50RR CHORSHI 80-11 11/22/85C 12/25/85C CYCLE XI O 04 y y M42914 5-59 05/08/80 L 12/23/85C UTAGE DMD1 DONOMEM y
j ACTION ITEM: OYSTER CREEK - LEAKAGE DETECTION 10/01/82 L 1 BND1 DONOMEN 08/23/85C 01/06/86C 01/04/86C IPSAR 4.16 04 M49001 94/27/84X PRIA MCKENNA PBS$ MICHAELS 86/07/45X U
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INF0RMAT.ON TRACKINO $YSTEM PAv NO.8 58 R-12e8473 vel REOULAT0RY o 9 DIVISION OF LICENSING RUN DATE8 82/03/86 -
LICENSING ACTIONS REPORT (HEAD 0UARTERS) R FACILITYs OYSTER CREEK 1 SC T 10 rN Y P RAI g MULTI REV RESPONSE SE INPUT LIC ACT AD TAC PLANT INIT P NOTICE R DATE DATE IE EXPIRES 1 9398 REVIEMER RAI DATE DATE TER DATE ,C0f01ENTS NUMBER ACTION RIE, E m
g t:::u COMPLETED ACTIONS Muu (CONTINUATION)
ACTION ITEM: OYSTER CREEK - MATER PURITY SPECIFICATION $9/18/84C 11/21/85C 11/21/85C IPSAR 4.29 04 q 3 M49404 11/01/82 L 03/30/85 1 BND1 DON 0 HEN 94/27/84X RG 1.54 PRIA MCKENNA 84/07/85X PBS$ MICHAELS o
ACTION ITEM: OYSTER CREEK 1 - TECHNICAL SPECIFICATIONS COVERED BY OENERIC LETTERS 83-34, 83-37 FOR NUREG-9737 01/15/85X 11/22/85C RE9UESTS T 84 M54554 B-83 85/28/84 L 05/58/45 PAD 5 PATEL BND1 DONOMEN 11/22/85C 3 PBS$ ERICKSON 91/10/84X n 3 ORBM SCHOLL 11/22/85F 04 o
3 ACTION ITEM: OYSTER CREEK 1 - DIESEL OENERATOR BNDI DONOMENRELIABILITY TECN. SPECS. (OL 84-15) 19/07/85P 19/07/85C
,555845 D-19 09/28/84 94 n
'3 ACTION ITENs 10/22/84 OYSTER CREEK 11/15/85- RESPONSE TO IE BULLETIN 82-03 BND1 DOM 0 HEN 01/04/86C SYSTEM
- REACTOR COOLANT GS/23/85C 01/06/86C LEAKAGE M54754 87/12/85X DePN CARUSD Sf/94/84P PBIA MCKENNA O 3
ACTION ITEM: OYSTER CREEK - RELAX FRE00E90CY OF AUDITING GUALITY ASSURANCE PROGRAM 87/02/85C 11/96/85C REGION I - 94 M56755 10/24/84 03/27/85 BNB1 DONOMEN 07/02/85P g RE01 CAPHTON g RE01 NAVERKAM 96/t3/85C RE01 NAPUDA 06/13/85C .
O 9 ACTION ITEMS OYSTER CREEK - FEBRUARY 11, 1985 CNANGES TO ISI/IST 18/18/85C 10/18/85C REGION 1 94
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REGI MAVERKAMP 10/18/85P g REOS KUCHARSKI RE01 JOHNSON 88/17/45C l
.U ACTION ITEMS OYSTER CREEK - CNANGES FOR CLARIFICATION AND CONSISTENCY AMONG ACCIDENT11/99/85C MONITORING INSTRUMENTATION 12/09/85C 04-M56918 82/11/85 85/30/85 BNDt DONOMEN l
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DIVISION OF LICENSING RUN DATE: 02/03/86 l
i LICENSING ACTIONS REPORT j (NEAD9UARTERS) '
e FACILITY: OYSTER CAEEK 1 i
T SC MULTI Y P RAI 10 e TAC PLANT INIT P NOTICE R REV RESPONSE SE INPUT LIC ACT AD RIE E EXPIRES 1 DRQH REVIEMER RAI DATE DATE TER DATE DATE DATE CON 9ENTS JE l NUMBER ACTION Una COMPLETED ACTIONS unu (CONTINUATION) , e ACTION ITEM: OYSTER CREEK - SALP MEETING FOR SEPTEMBER 1985 10/28/85C 10/28/85C 04 g -
i M57472 04/25/85 SND1 DONOMEN '
PSIA MCKENNA 08/09/85C l
I i ACTION ITEM: OYSTER CREEK - NEN ANALYSIS OF MAXIMUM DRYWELL TEMPERATURE PRIOR TO LOCA- g M59052 07/02/85 BNDS DONONEW 08/Of/85C 11/22/85C 11/22/85C REGUESTS T 84 j
BNPS NOTAFRANCESC 08/14/85C S D
l ACTION ITEM OYSTER CREEK - REVIEN OF DELAMINATION BNPS WITT GF COATING FROM PIPING IN EMER0ENCY 09/20/85X SERVICE NATER 01/06/86C REGUESTS L 04 ,
- M59282 BND1 DONOMEN O1/06/84C ONO TERM /-
! BNPS MULMAN 01/06/84P eg ACTION ITEM OYSTER CREEK - LIMITATION ON OVERTIME AS IDENTIFIED IN OL83-02 08/02/85X 11/19/85C RESUESTS T 84 M59300 07/22/85 09/28/85 PAD 4 NOOD g BND1 DON 0 HEN 11/19/85C 3 j
1 1, ACTION ITEMS OYSTER CREEK - DELETE DAILY CHANNEL CNECK FOR INSTRUMENTATION TO BE INSTALLEB IN 10M OUTAGE y i M59814 09/30/85 11/25/85 BND1 DONONEN 11/30/85C 11/30/85C 04 i
j, ACTION ITEMS OYSTER CREEK - REVISE ACTION STATEMENT FOR LON-LON REACTOR NATER LEVEL CHANNEL INOPERASILITY-CYCLE 10M OUTAdd y 11/19/85F 11/19/85C 04 10/11/85 SMD1 DONONEN l M59895
' ACTION ITEMS OYSTER CREEK - CROSS REFERENCE INDEXING SYSTEM FOR IPSAR SECTION 4.26.2, INSTRUM. FOR RTS TESTINO i M60151 10/22/85 BNet DONONEN 01/f7/86C 01/17/86C
- 04 PBIA MCKENNA 01/28/86C j_ '
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!' ACTION ITEM: OYSTER CREEK - JUSTIFICATION FOR MOT REVISING 50.72/73 TECHNICAL SPECIFICATIONS 12/18/85C 12/18/85C 04 i M60154 10/21/85 DWD1 DONOMEN 4
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' ATTACHMENT 3 Future Licensee Technical Specification Change Requests (TSCR)
The licensee is planning to propose the following TSCR soon:
(a) Excess Flow Check Valves: The TS require the licensee to verify that these valves are open but do not provide criteria for determining this. The TSCR will propose criteria. This is needed before the restart from Cycle 11R outage.
(b) Diesel Generatoe Batteries: The TS require twelve 2-volt cell batteries and the licensee wants to install two 12-volt cell batteries. The licensee needs it as soon as the staff can' review the TSCR because the licensee has found out that it cannot purchase replacement batteries that meet the TS.
(c) Diesel Generator Loading: The TS require loading the diesel generators during normal surveillance. The TSCR will request not loading the diesel generators in certain cases to provide additional assurance the diesels are available for an accident during certain conditions. The licensee will request review within 2 months of the TSCR submittal.
(d) Rod Worth Minimizer (RWM): The licensee is installing a new RWM in the Cycle 11R outage because of problems experienced with the present system. The TSCR will request a change to allow startup without a RWM and with appropriate administrative controls in case the new RWM is not operational before the restart from the outage. The licensee will need it before the restart from the Cycle 11R out:ge.
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Attachment 4
(
High Priority Actions dated January 22, 1986 1986 Staff Licensee /se Branch Target Date Status #
TAC Title Plant System February
- 02 60153 Cancel Modification Torus Pool Temperature Monitoring Plant System February
- 02 60152 Cancel Modifications Torus Pool Thermal Mixing Revise Opera'oility of Reactor System May 01 59935 low-low RCS Water Level February
- 02 59830 Cancel Modification to Plant System Install Pressure Relief Plant System February
- 02 59829 Cancel Modification to
- Upgrade N2 Purge / Vent
(' System Engineering March
- 01 59828 Cancel of Purge / Vent Valve Replacement 59758 Scope Change for Reactor System March
- 02 Recirculation Loop Interlock, II.K.3.19 Ceferments from Cycle BPD#1 February
- 01 59400 11R Outage 59342 Exemption to RCS Vent Reactor System March
- 02 Plant System February
- 02 58018 Generic Letter 84-09 Integrated Safety May 01 58004 Discrepancy in SEP**
Drawings Assess Directorate Tornado Missile Damage Plant System March *** 02 49394
- SEP Emergency Condenser BPD#1 J un e * *
- 01 49397 Isolation Integrated Safety December 1985 02 49398 Seismic Design - SEP**
Assess Directorate Integrated Safety December 1985 02 49392 Wind Loads - SEP**
Assess Directorate
'~ l f
1986 Staff Licensee /se Target Date Status #
Title Branch TAC Reactor System February
- 02 46466 Control Room Habitability
- 02 Inservice Testing Engineering 11270 April
- 01 Appendix I TS BPD#1 08100
- Actions involved with Cycle 11R outage which begins April 1986.
- Involved with licensee's work on IE Bulletins 79-14/02 and/or package is at Director's desk.
- Old SEP reviews with licensee's submittals with reviewer and needed for FTOL conversion.
- This needs to be scheduled by the branch because plant is in the 7th year of the 10 year cycle.
- 01 = licensee, 02 = staff reviewer, 03 = ORPM, 05 = licensing action in concurrence.
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Attachment 5 STATUS OF LICENSING ACTIONS February 20, 1986 Technical Assignment (TAC) TAC Numbers . Change
- Active as of 10/1/85 62 --
New TAC since 10/1/85 22- +5 Total TAC 84 +5 Completed TAC since 10/1/85 (04) ?? +3 TAC needing Licensing response (01) 12 -1 TAC-under staff review (02) 32 -4 TAC with staff Project Manager (03) 10 +4 TAC in staff concurrence (05) 08 +3 Total TAC 84 +5
- From previous monthly progress review meeting
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. ATTACMENT 7
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STAFF'S LETTERS OF RE0llESTS FOR INFORMATION Letter .
RFI Request RFI Submittal Date Subject Date Date 1/27/86 Cancellation of 3/07/86 Licensee requests Purge and Vent Valve meeting Replacement 1/21/86 Containment Purging and Venting during Plant Operation
- Licensee requests 1/09/86 Draft TER for IPSAR Section 4.11 meeting 1/06/86 0 elimination of Coating
- on ESW Piping 11/30/85 Reactor Water Level Before Cycle 11R 01/23/86 Meeting
-Instrumentation outage comencement Channel Check 11/24/85 NUREG-0737 TS Before restart from (GL 83-36): 4 items Cycle 11R outage 11/2?/85 Maximum Orywell Before restart from Temperature Cycle 11R outage 11/71/85 Water Purity
- 10/24/85 Draft TER for
- Phone Call on Salem ATWS 1.2 12/ /85
'8/30/85 Isolation Condenser 02/03/86 Vent Exemotion 8/22/85 PETS (Meetingminutes) 9/01/85 7/15/85 IPSAR Section 4.26.2 9/07/85 10/22/85 6/12/85 Surveillance Capsule 10/31/85 10/ /85 5/30/85 NUREG-0737 TS Before restart (GL 83-02h 3 items from Cycle 11R II .E.4.2.7, II .K.3.19 outage II.E.4.1 05/30/85 10 CFR 50.72/73: 3 items 10/21/85**
04/29/85 GL 84-09 6/30/85 08/14/85**
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! _ 2 i Letter RFI Recuest RFI Submittal Date Subject Date Date [
04/19/85 TMI II.B.2.2 5/30/85 09/09/85
- 04/11/85 Wetwell/drywell 8/30/85 Vacuum Breakers 1
i 04/05/85' GL 83-28 7/5/85 and 8/5/85 10/23/85 l r
- To be negotiated with the staff Project Manager .
! **Information remains to be submitted.
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SUPPRESSION POOL THERMAL MIXING MODIFICATIONS REQUEST FOR I:4 FORMATION To provide the basis for postponing and eventually cancelling the requirements for suppression pool temperature monitorino local to the quenchers and the thermal mixing modifications for the suppression pool the following additional information is needed:
- 1. Will the suppression pool temperature limits be relaxed, tightened or remain the same with the elimination of the SRV discharge temperature limit?
- 2. What are the temperature limits needed to provide adeouate NPSH for the core spray pumps under applicable accident conditions, or if not core sprav pump NPSH, the temperature limits for the next most restrictive suDDression pool limit?
- 3. What is ynur basis for determining the adequacy of the existing tenDerature monitoring system in providing information concernino the local temperatures to the core spray pump suction header?
4 What is your basis for determining the adequacy of existino suppression pool mixing under applicable accident conditions in providino suppression pool temperatures local to core spray pump suction header which are indicative of data obtained from the existing temperature monitoring systen?
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