ML20237L612
| ML20237L612 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 08/19/1987 |
| From: | Gallagher J PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | Butler W Office of Nuclear Reactor Regulation |
| References | |
| GL-83-28, NUDOCS 8708280178 | |
| Download: ML20237L612 (5) | |
Text
e PHILADELPHIA ELECTRIC COMPANY
)
2301 MARKET STREET P.O. BOX 8699 j
PHILADELPHIA A. PA.19101 (215) 841 5001 August 19, 1987 sosem w. cattaowca ocT.".l"o"'..'~l...
Docket Nos. 50-277 50-278 j
I Mr. Walter Butler Project Directorate I-2 Division of Reactor Projects I/II i
U.S. Nuclear Regulatory Commission j
ATTN:
Document Control Desk l
Washington, D.C.
20555
)
SUBJECT:
Peach Bottom Atomic Power Station Units 2 and 3 Generic Letter 83-28, Item 1.2,
" Post Trip Review:
Data and Information Capability" i
Dear Mr. Butler:
l On July 8, 1987, a conference call was held between Philadelphia Electric Company personnel and Nuclear Regulatory Commission staff.
The conference call concerned Item 1.2,
" Post Trip Review: Data and Information Capabilities" of Generic Letter 83-28 (July 8, 1983) for the Peach Bottom Atomic Power Station, Units 2 and 3.
Previous Nuclear Regulatory Commission correspondence concerning Item 1.2 is included in Nuclear Regulatory Commission letters dated July 10, 1985 and March 5, 1986.
Our responses to these letters were provided in a letter dated October 16, 1985 and in a meeting held on May 22, 1986 between G. Gears (Nuclear Regulatory Commission), T. Johnson (Nuclear Regulatory Commission) and Philadelphia Electric Company personnel.
I l
At the May 22, 1986 meeting, Philadelphia Electric Company personnel described the existing post-trip review process.
The schedule for installation of a new process computer s
schedule was also discussed.
The July 8, 1987 conference call was held to clarify the remaining open items necessary to close Item 1.2.
During this
/
fy](9 i
B708280178 870019 IO l
PDR ADOCK 05000277
\\
l P
PDR j
l
____________j
]
s, Mr.' Walter Butler August 19, 1987 Page 2 conference call, Philadelphia Electric Company was asked to do the following:
Item Provide an overview of the new process computer.
Response
l
)
Philadelphia Electric is replacing'the existing Honeywell 4020 computer with a unitized.and redundant VAX 8530.
])
l The new system will perform all existing functions such as' alarming, balance of plant (BOP). logging, sequence-of-events logging, nuclear steam system calculations and new functions.such
]
as the Safety Parameter Display System (SPDS).
Our system i
supplier is Science' Applications International Corporation who i
also was the system supplier for similar work at the Cooper &
D Duane Arnold Power Stations.
The system is being designed to meet the availability goals required by'the SPDS..The system's I
analog and digital input subsystem will be capable of scanning at rates sufficient to meet the ten second analog and 100 milliseconds sequence of events sampling rates required for post-3 trip monitoring.
Item Review our conformance with the " good practices" approach identified in the Nuclear Regulatory Commission letter dated July 10, 1985.
Response
l The Nuclear Regulatory Commission letter dated July 10, 1985, provided a " good practices" approach-listing of design criteria for the post-trip review data and information capability.
With the completion of the installation of the new plant process computer, Philadelphia Electric Company will: meet all of the design criteria identified in the July 10, 1985' letter except for the method of display of the turbine bypass valve-l position parameter for which an alternate method'has been I
selected as discussed below.
4 I
J j
)
I i
Mr. Walter Butler August 19, 1987 Page 3 I
l The turbine bypass valve position parameter is being recorded as an analog point in our post-trip data log, not as a sequence-of-events point as recommended in the letter.
While time resolution will drop from 100 milliseconds to 10 seconds (analog scan period for this parameter) this will provide additional information with respect to the intermediate valve position.
Additional clarification is also necessary with regards to the containment isolation parpmeter.
The plant process computer will log the main steam isolation valve position as well as the initiating signals.for Group I, II and III containment isolation as defined in Technical Specification Table 3.7.1.
The process computer is not logging logic output signals nor the valve positions for the remaining valves in the sequence-of-events log.
This remaining valve position information will be included in the Safety Parameter Display System which is an integral part of the new process computer.
i i
Item Provide a schedule for the new plant computer.
l
Response
The plant process computer and Safety Parameter Display System will be operational following the third refueling outage after 1985 for both Units 2 and 3.
Based on our current outage schedule, this translates to 1990/1991 dates.
The computer hardware for Unit 3 will be installed during the upcoming Unit 3 outage scheduled for late 1987.
The new and old process computers would then be operated in parallel for one cycle with the new computer system undergoing testing and being used for operator training.
It is our intent that by early 1989, the check out process will have progressed to a point where the post-trip data review function will be available either in the Administration Building or Control Room, depending on the installation sequence chosen.
Following the check out operation, the installation of the new system will be considered complete after any temporarily located equipment is placed in its final location during the next refueling outage which is currently scheduled for mid-1990.
1
Mr. Walter Butler August 19, 1987 Page 4 Utilizing Unit 3 as a guide, this process will be repeated for Unit 2 during the next Unit refueling outage scheduled for late 1989.
The parallel test for Unit 2 will be
{
run for one cycle followed by final location installation which will occur during the following Unit 2 outage which is scheduled for early 1991.
I It should be noted that based on our current outage i
schedule, the installation and check out process will be complete by 1990 for Unit 3 and 1991 for Unit 2.
The detailed construction and testing schedule may vary.
Based on the previously mentioned conference call of July 8, 1987, as documented herein, it is Philadelphia Electric's understanding that the clarification to the two plant parameters discussed ~above and the company's plans in response to Item 1.2 are acceptable.
Additionally, no interim upgrading will be necessary for the existing methodology of post-trip review.
If you have any questions please do not hesitate to i
contact us.
Very truly yours,
]
I
} &J' cc: Addressee T. P. Johnson, Resident Site Inspector 1
\\
9' iIECEIVED I
AUG2 81987> C vb. "bEFEdEl?" ' )
ra 4
~
- - _ _ _ _ _ _ _ _ _ _