ML20206P761
| ML20206P761 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 08/22/1986 |
| From: | Donohew J Office of Nuclear Reactor Regulation |
| To: | Fiedler P GENERAL PUBLIC UTILITIES CORP. |
| References | |
| TAC-61242, NUDOCS 8608270308 | |
| Download: ML20206P761 (10) | |
Text
4.9 UNITED STATES N
NUCLEAR REGULATORY COMMISSION h
WASHtNGTON, D. C. 20555
%..... [
August 22, 1986 Docket No. 50-219 Mr. P. B. Fiedler Vice President & Director Oyster Creek Nuclear Generating Station Post Office Box 388 Forked River, New Jersey 08731
Dear Mr. Fiedler:
SUBJECT:
IMPLEMENTATION OF GENERIC REQUIREMENTS (TAC 61242)
Re: Oyster Creek Nuclear Generating Station On April 18, 1986, we requested that you assist us in developing the documentation on the status of the implementation of approved regulatory required improver. eats at Oyster Creek. These improvenents have core out of the resolution of generic safety issues between GPU Nuclear Corporation and Jersey Central Power and light Company (the licensees) and the staff.
They have changed the licensing design basis for Oyster Creek since the operating license was issued on August 1,1969. These generic safety issues are multi-plant actions (MPA) as identified in the enclosure to our April 18, 1986, letter. The design of the plant in 1969 and the completion of these improvements on the agreed upon schedule form the licensing basis for the continued operation of Oyster Creek. Therefore, it is necessary for NRC to know that these improvements have been fully implemented as scheduled.
In your responses dated June 3 and 27, 1986, you provided the list of MPA.
For each MPA, you identified the status and implementation date or marked it with an asterisk. The asterisk meant that there was not a. clear identi#ication of thr MPA and that you were requesting assistance from the s
l staff in identifying the MPA.
Enclosed is a table of the MPA that you requested assistance from thte staff in identifying. The column on the resolution of the MPA explains the basis for the MPA and its resolution.
In several cases, the MPA was closed ott without i
a letter being sent to you. These MPA had no action for you to complete as part of the MPA and are marked as "NA" or not applicable to Oyster Creek.
The resolution of the MPA given in the table is based on the documents in the staff's Document Control System.
Please review the enclosed table. As snon as possible but within 120 days of j
receipt of this letter, please confirm or correct, by letter, the MPA status and implementation dates given in the enclosed table.
I request that you do
~
h i
8608270308 860822 f
PDR ADOCK 05030219 P
PDR r
August 22, 1986 P. B. Fiedler
-?-
this by updating the table in your letter dated June 27, 1986, based on your review of the information in the enclosed table.
Sincerely, W
1
/ Jac N. Donohew,' Jr., Project Manager N BWR Pro,iect Directorate #1 Division of BWR Licensing
Enclosure:
As stated cc w! enclosure:
See next page DISTRIBUTION Docket File NRC~PDR' Local PDR BWD1 Reading R. Bernero OGC-BETH (Info only)
E. Jordan B. Grimes J. Partlow J. Donohew C. Jamerson J. Zwolinski BWD1 Staff ACRS (10)
OC File R. Emch K. Pulsipher i
0FC
- DBL:BWD1
- DBL 3:
1
- DBL:B M
..___:...f ______:____________:___.________:_...________:_________._
i _____:_________
N
- JZwolinski
!NAME:CJamerso I
- J@
_:__A.________:____________:____________:-__.._______:___________:___________
DATE :8/Q1/86
- 8/)1/86
- 8h:1./86 0FFICIAL RECORD COPY
Mr. P. B. Fiedler Oyster Creek Nuclear Oyster Creek Nuclear Generatina Station Generating Station cc:
Mr. Ernest L. Alake, Jr.
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.R. Liberman, Esquire Commissioner Rishop, 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 Mr. David Scott, Acting Chief Regional Administrator, Region I Pureau of Nuclear Engineering U.S. Nuclear Regulatory Commission Department of Environnental Quality 631 Park Avenue 380 Scotch Road King of Prussia, Pennsylvania 19406 Trenton, New Jersey 08628 PWR Licensing Manager GPU Nuclear 100 Interpace Parkway Parsippany, New Jersey 07054 Deputy Attorney General State of New Jersey Department of Law and Public Safety i
36 West State Street - CH 112 Trenton, New Jersey 08625 Mayor Lacey Township 818 West Lacey Road 1
Forked River, New Jersey 08731 Licensino Manacer Oyster Creek Nuclear Generating Station Mail Stop: Site Emergency Bldg.
P. O. Box 388 Forked River, New Jersey 08731 i
I TABLE IMPLEMENTATION OF GENERIC REOUIREMENTS I
Lic. Act.
Implementation MPA #
TAC #
Comolete Resolution of MPA MPA Status Date A-03 M06908 09/14/79C License Amendment No. 41 dated Complete 09/14/79 4/14/79 incorporated the Plant Security Plan in the license.
This completes MPA A-03.
A-04 M06104 01/01/74C Resolution of this MPA is throuoh NA NA TAC M08678. TAC M06104 was closed out without a letter to the licensee and without any action required of the licensee.
A-09 M11366 01/12/78C This MPA was the data the licensee Complete 01/12/78 submitted by letter dated 01/12/78, on the materials used iri reactor vessel fabrication from the reactor materials surveillance program. The data was in response to the staff's letters dated 05/20/77 and 10/28/77.
This data closed the MPA. TAC M11366 was closed out without a letter to the licensee and without any further action required of the licensee.
A-15 M12651 01/07/80C On 1/7/80, the staff issued a generic Completer 01/07/802
~
letter on quality assurance require-ments on diesel generator fuel oil.
The generic letter did not require a response from the licensee unless the licensee did not comply with the require-ments in the generic letter to have diesel gene.rator.fcel oil in the plant Ouality Assurance Program. __
TABLE IMPLEMENTATION OF GENERIC RE0VIREMENTS Lic. Act.
Implementation MPA #
TAC #
Complete Resolution of MPA MPA Status Date B-05 M08224 10/17/79C The resolution of this MPA is throuch NA NA TAC M46668. This TAC M08224 was closed out with the issuance of IE Bulletin 79-13, Revision 2, on cracks in the feedwater system piping. There was not a letter to the licensee.
B-06 M08200 09/21/79C This MPA was resolved with the Complete 09/21/79 licensee's letter of 9/21/79 statino it had no Tar 9et Rock safety relief valves at Oyster Creek. This letter was in response to the staff's generic letter dated 7/16/79.
B-20 M10287 01/16/81C The resolution of this MPA is throuah NA NA containment leakaae due to seal deterio-ration in TAC M42613, MPA B-24.
TAC M10287 was closed out without a letter to the.
licensee and without any action required of the licensee.
B-21 M10349 02/09/82C This MPA was closed out by a staff NA NA memorandum dateu 2/9/82, without any action required by the licensee and without a letter to the licensee. This issue was made part of the staff's implementation of the recommendations of NUREG-0660 on Task Action A-30.
TABLE IMPLEMENTATION OF GENERIC REQtlIREMENTS Lic. Act.
Complete Resolution of MPA MPA Status Date B-24 M10191 08/25/80C The resolution of this MPA is through NA NA TAC M42613. This TAC M10191 was closed out without a letter to the licensee and without any action required of the licensee.
B-27 M10891 08/22/79C The resolution of this MPA was through Complete 3 08/22/793 the ceneric letter dated 8/22/79 to the licensee. The staff concluded that the Oyster Creek off-gas system provided reasonable assurance that the potential for external explosions was minimized.
B-27 M07404 07/01/78C The resolution of this MPA was through NA NA TAC M10891, MPA R-27. This TAC M07404 was closed out without a letter to the licensee and without any action required of the licensee.
?
B-29 M11015 11/30/78C The resolution of this MPA was through Complete 11/30/78 the staff's Safety Evaluation dated 11/30/78. The staff concluded a feed-water trip on high reactor water leval was not necessary.
B-46 M42083 08/27/81C The resolution of this MPA was throuch Complete 8/27/81 the staff's Safety Evaluation dated 8/27/81. The staff decided to dis-continue its monitoring of inspections of turbine low pressure discs for cracks. __
l
_..m__.
TABLE IMPLEMENTATION OF GENERIC RE0llIREMENTS Lic. Act.
Implementation MPA #
TAC #
Complete Resolution of MPA MPA Status Date B-47 M12699 09/11/80C The resolution of this MPA was through Complete 09/11/80 the staff's Safety Evaluation dated 9/11/80. This MPA was the review of the licensee's response to the staff's generic letter dated 11/9/79 on the portions of the ECCS evaluation models dealing with fuel cladding swelling and incidence of fuel pin rupture.
The staff concluded that no further action was required.
B-61 M42692 07/28/82C This MPA was closed out by the staff NA NA internal memorandum dated 7/28/82 without a letter to the licensee and without any action required by the licensee.
By staff memorandum dated 6/22/82, the staff stated that the plant met the concerns of TE Bulletin 79-27 which is MPA B-61.
)
5 5-B-62 M42763 06/21/82C This MPA was resolved throuah the staff Complete 06/21/82 Safety Evaluation dated 6/21/82 to 0IE/
NRC on IE Bulletin 80-06.
No letter was sent to the licensee and no actions were required of the licensee.
B-70 M46623 05/25/82C This MPA was closed cut without a' letter NA NA to the licensee and without any actions required of the licensee. This issue was l
transferred to DSR0/NRR for prioritization.. - __ J
TABLE IMPLEMENTATION OF GENERIC RE0tlIPEMENTS Lic. Act.
Implementation MPA #
TAC #
Complete Resolution of MPA MPA Status Date 0-11 M10070 10/13/78C The resolution of this MPA was throuah Complete 10/13/78 the staff's Safety Evaluation dated 10/13/78. This reviewed the licensee's response to the staff's letter dated 11/23/76 to assess the higher fission qas release for fuel burnups above 20,000 MWD /MT.
No letter was sent to the licensee.
The staff concluded that no licensing action was needed for operating reactors.
5-12 M07961 07/20/84C The resolution of this MPA was through Complete 07/20/84 the staff's Safety Evaluation dated 7/20/84 which concluded that the core spray -
effectiveness in a steam environment was acceptanle. One open issue on the modifica-tions made to the small break evaluation model was resolved in Section 2.3 of the staff's Safety Evaluation dated 8/27/84 for
)
' Amendment 75, " Cycle 10 Reload." This MPA required the core spray system nozzle coverage he re-analyzed to reflect the steam environment in a reactor core.
D-15 M12291 02/02/84C This MPA was closed out by the staff NA NA internal memorandum dated 2/2/84 without a letter to the licensee. Based on the staff's internal Safety Evaluation dated 12/19/79 any actions to be required of the licensee would be included under Item II.C.3 of NilREG-0660.
i TARLE i
IMPLEMENTATION OF GENERIC REQUIREMENTS Lic. Act.
Implementation MPA #
TAC #
Complete Resolution of MPA MPA Status Date F-18 M44801 06/10/80C The resolution of this MPA was the Pro.iected Cycle 12R Outage Licensee's commitment letter dated 6/10/80.
This was responding to the staff's Safety Evaluation dated 5/8/00 (item 2.1.5.a) on the licensee's implementation of NUREG-0578.
This MPA is that the containment isolation purge and vent system meet single failure criteria for operation and isolation and the containment valves be subject to the require-ments of Appendiv J and the Technical Specifications modi 9ed accordinnly (Generic letter 83-02). This is Item 2.1.5.a of NUREG-0578 dated July 1979. The licensee requested cancellation of its commitment in its letter of 9/24/85. The staff denied this request in its letter of May 5,1986, and required the licensee to install the modifications to its nitrogen purce/ vent system by the Cycle 12R outane.
The licensee has requested a meetina with the staff to' respond to the staff's letter.
F-19 M44872 08/31/83C The resolution of this MPA is explained in Pro.iected Cycle 11R Outage (1) Section 2.5 of the staff's Safety Evalua-tion dated 1/21/86 for MPA B-24 and (2) the staff's Safety Evaluation dated 8/31/R3.
The licensee is to install in the C.ycle 11R outage the high range radiation signal (TMI item II.E.4.2.7) to isolate the containment purge and vent system and propose appropriate TABLE IMPLEMENTATION OF GENERIC RE0llIREMENTS Lic. Act.
Implementation MPA #
TAC #
Complete Resolution of MPA MPA Status Date technical specification (see Generic Letter 83-02). This is to meet the schedule in Confirmatory Order dated June 17, 1983.
The licensee has requested in its letter dated 9/4/85 not to replace its containment purge and vent valves (TMI item II.E.4.2.6).
This is under review for completion before the restart from the Cycle IIR outage.
F-66 M46182 07/30/82C This MPA was closed out by the staff NA NA without a letter to the licensee and without any action required of the licensee.
I Cycle 11R outage means the Cycle 11 Refueling outape.
2 Licensee has diesel generator fuel oil in the plant Ouality Assurance Program.
3 Licensee committed to modify an existing valve on the drain line upstream of the sump and to change procedures to require closing this valve immediately af ter a pres:ure transient in the off-gas system.
Licensee committed to install a containment high range radiation signal to isolate the containment vent and purge isolation valves. See the staff's letter dated 8/4/86 denying the licensee request to cancel this installation.
5 Licensee committed to perform verification tests to verify that all associated equipment is consistent with the reviewed schematics before restart from Cycle 9R outage. s