ML18086B128
| ML18086B128 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 12/07/1981 |
| From: | Schneider F Public Service Enterprise Group |
| To: | |
| Shared Package | |
| ML18086B127 | List: |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.B.3, TASK-2.F.1, TASK-2.F.2, TASK-TM LCR-81-23, NUDOCS 8112140247 | |
| Download: ML18086B128 (6) | |
Text
Ref. LCR 81-23 U.S. NUCLEAR REGULATORY COMMISSION DOCKET NO. 50-311 PUBLIC SERVICE ELECTRIC AND GAS COMPANY FACILITY OPERATING LICENSE DPR-75 NO. 2 UNIT SALEM NUCLEAR GENERATING STATION Public Service Electric and Gas Company hereby submits proposed changes to Facility Operating License DPR-75 for Salem Nuclear Generating Station, Unit No. 2.
This change request relates to the completion dates for certain TMI-related items identified in Section 2.C of the License.
8112140247 811207 PDR ADOCK 05000311)
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. PDR Respectfully submitted, PUBLIC SERVICE ELECTRIC AND GAS COMPANY By:
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FREDERICK W. SCHNEIDER VICE PRESIDENT
Ref. LCR 81-23 STATE OF NEW JERSEY}
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SS:
COUNTY OF ESSEX
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FREDERICK W. SCHNEIDER, being duly sworn according to law deposes and says:
I am a Vice President of Public Service Electric and Gas Company, and as such, I signed the request for change to FACILITY OPERATING LICENSE DPR-75.
The matters set forth in said change request are true to the best of my knowledge, information, and belief.
Subscribed and sworn to before me this a day of.JJt<'J/1/1 ).Lf.;t,,. 1981
~Ld/ttALL fi_ /;t,ctr~t1JA ~a) c2otary Public of New Jersey My Commission expires on {)tt,. /, !C/?3
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REQUEST FOR AMENDMENT 81-23 FACILITY OPERATING LICENSE DPR-75 NO. 2 UNIT SALEM NUCLEAR GENERATING STATION DOCKET NO. 50-311 Paragraph 2.C(25)(d) Post-Accident Sampling An order was placed in June, 1980 for the Sentry post-accident sampling system.
Design changes and new material requirements were identified as the engineering and design of the system progressed.
In May, 1981, as the design pro~ressed, six additional valves were identified as being required.
An order was placed immediately, but delivery cannot be made until June, 1982.
Every effort has been made to expedite these valves, however, the manufacturer cannot improve on the June date.
Additionally, the partitioning system has been under development for some time by Sentry and has just recently been made available to us, with delivery scheduled for April, 1982.
Some progress in the installati~n was made during the periods when Salem 2 was not operating.
Pre~ently, the inside containment work is approximately 75% complete and the outside containment work is approximately 20% complete.
Approximately four weeks outage time is required to complete the installation.
However, there is no planned outag.e for Salem 2 until its first refueling, which is presently scheduled to commence in January, 1983.
Because of the expected material delivery dates and the unit outage time required to.complete the installation, we request the required completion date -'for the Post-Accident Sampling System be deferred until the completion of the first refueling outage.
Should a forced outage of sufficient duration occur in the interim, every effort will be made to complete this work.
It is therefore requested that paragraph 2.C(25)(d) be revised to read:
"(d)
Post-Accident Sampling (Section 22.3, II.B.3)
PSE&G shall complete corrective actions needed to provide the capability to promptly obtain and perform radioisotopic and chemical analysis of reactor coolant and containment atmosphere samples under degraded core conditions without excessive exposure no later than prior to startup following the first refueling outage."
' ".' Interim procedures for post-accident sampling and analysis of reactor coolant and containment atmosphere are presently in use.
These procedures were approved by the NRC staff for interim use in SER Supplement S, Section 22.2 (II.B.3).
Therefore, this change in completion date causes no. undue.
risk to the health and.safety of the public.
Paragraph 2.C(25)(h) Additional Accident Monitoring Instrumentation Engineering and design of the containment high range radia-tion monitor was completed in March, 1981 and installation is approximately 95% complete at the present time.
Instal-lation of environmentally qualified connectors and final t*esting remains to be compl~ted. The environmentally quali-fied connectors are scheduled for delivery by December 1, 1981.
Approximately two weeks outage time is required to complete the installation.
However, there is no planned outage for Salem 2 until its first refueling, which is presently sched-uled to commence in January, 1983.
Because of the expected material delivery dates and the unit outage time required to complete the installation, we request the required comple-tion date for the containment high range radiation monitor be def erred until the completion of the first refueling out-age.
Should a forced outage of sufficient duration occur in the interim, every effort will be made to complete this work.
At the.time the noble gas monitor and iodine/particulate sampling and analysis capability were identified as requirements, an engineering investigation was initiated to determin~ the availability of qualified equipment.
PSE&G collaborated with other licensees and EPRI in this effort, but it was not until July, 1981 that qualified equipment could be located and ordered.
This equipment is scheduled for delivery in late December, 1981.
Approximately eight weeks outage time is required to com-plete the installation of the noble gas monitor.
- However, there is no planned outage for Salem 2 until its first re-fueling, which is presently scheduled to commence in Jan-uary, 1983.
Because of the expected material delivery dates and the unit outage time required to complete the installa-tion, we request the required completion date for the noble gas monitor be deferred until the completion of the first refueling outage.. Should a forced outage of sufficient duration occur in the interim, every effort will be made to complete this work.
Approximately ten weeks time is required for installation of the iodine/particulate sampling equipment, although a unit outage is not required.
Because of the expected material delivery date and the time required to install this equipment, we request the required completion date for this item be deferred until June 1, 1982.
It is therefore requested that paragraphs 2.C(25)(h), (iv),
and (v) be revised to read:
- ch)
Additional Accident Monitoring Instrumentation isection 22.3, II.F.1J_
PSE&G shall install and demonstrate the operabil-ity of instruments for continuous indication in the control room of the following variables.
Each item shall be completed by the specified date in the condition:
(iv) Containment gamma radiation up to 107 rad/
hr. no later than prior to startup following the first refueling outage; and (v)
Noble gas effluent from each potential re-lease point from normal concentrations to 105 uCi/cc (Xe-133) no later than prior to startup following the first refueling outage.
PSE&G shall provide the capability to con-tinuousl~ sample gaseous effluents and ana-lyze these samples no later than June 1, 1982 *.
Until the above installation is completed, PSE&G shall use interim monitoring proce-dures and equipment.*
Interim containment radiation monitoring is provided with the existing high range (107 R/hr) containment radiation monitor.
A system for monitoring noble gas effluents in concentra-tions up to 100 uCi/c is currently installed, as well as an interim system to continuously sample gaseous effluents.
The capability to analyze these samples for radioiodines and particulates also exists.
I I
- The measures identified above were approved by the NRC staff for interim use in SER Supplement S, Section 22.3 (II.F.1).
These changes in completion dates, therefore, caus.e no undue risk to the health and safety of the public.
Paragraph 2.C(25)(i) Inadequate Core Cooling Instruments The Reactor Vessel Level Instrumentation System was ordered from Westinghouse in August, 1980 **
Final detail design of the system is essentially complete at this time, and the remaining material required for this system is scheduled to be delivered in December, 1981.
In order to complete this modification, the reactor vessel head must be removed and the primary loop drained to make the necessary connections.
Since plant conditions of this nature occur normally during refueling outages, we request that the required completion date for the Reactor Vessel Level Instrumentation System be deferred until completion of first refueling outage.
It is therefore requested that paragraph 2.C(25)(i) be re-vised to read:
"(i)
Inadequate Core ~ooling Instruments (Section 22.3, II.F.2)
PSE&G shall install and demonstrate the operabil-ity of additional instruments or controls needed to supplement installed equipment in order to provide unambiguous, easy-to-interpret indication of inadequate core cooling no later than prior to startup following the first refueling outage."
The existing instrumentation to detect inadequate core cool-ing (subcooling meter) and procedures were approved by the NRC staff for interim use in SER Supplement 5, Section 22.3 (II.F.2).
This change in completion date, therefore, causes no undue risk to the health and safety of the public.