ML20215C927
| ML20215C927 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 12/10/1986 |
| From: | GENERAL PUBLIC UTILITIES CORP. |
| To: | |
| Shared Package | |
| ML20215C925 | List: |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.F.2, TASK-TM NUDOCS 8612160014 | |
| Download: ML20215C927 (6) | |
Text
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I.
Technical Specification Change Pequest No.165 The Licensee requests that the following pages be inserted into the l
existing Technical Specification: 3-128 and 3-129; and replace existing pages iii and 4-7a.
II.
Reason for Change In accordance with NRC Order dated December 10, 1982, GPUN was directed to install Inadequate Core Cooling instrumentation which included a reactor coolant inventory trending system. This was to be done using the parameters specified in NUREG 0737, Item II.F.2.
This change incorporates requirements for the Reactor Coolant Inventory Trending System (RCITS).
III.
Safety Evaluation Justifying Change This Technical Specification Change Request (TSCR) addresses the operability requirements and calibration frequency for the RCITS.
The Safety Evaluation justification for RCITS is provided in the
{
December 10,1982 Order. This Technical Specification is adequate because the operator can obtain sufficient core cooling information from other indications such as Accident Monitoring Instrumentation (3.5.5), Saturation Margin and BIR0.
The RCITS is an information system which is intended to aid accident monitoring capability and thus does not reduce safety.
Therefore this change does not involve a reduction in the margin of safety.
Currently the channel output device for the level and void fraction is the plant computer. GPUN does not intend to formally track the availability of the plant computer as it does other Tech. Spec. time clocks. To date, the plant computer has not been unavailable for any duration that approached 30 days.
A failure of the plant computer is clearly indicated to the operators by the state of the CRT's in the control room which are used routinely and f requently by the operators.
Therefore there is no need to formally log the availability in the operator logs.
This Safety Evaluation only evaluates the change to the Technical Specifications. The evaluation of the hardware has been done previously and is under review by the NRC.
IV.
No Significant Hazards Considerations This proposed change is similar to example 11 of " Amendments Not Likely to Involve Significant Hazards Considerations," Federal Register Volume 48, No. 67 at 14870, dated April 6,1983.
8612160014 861210 DR ADOCK 05000289 PDR
_1 _
IV.
No Significant Hazards Considerations (Cont'd.)
Operation of Three Mile Island, Unit 1 with the proposed Techr.ical Specification Change Request would not:
(1)
Involve a significant increase in the probability or consequences of an accident previously evaluated.
The Reactor Coolant Inventory Trending System is neither credited nor required in the evaluated accidents and is not relied upon for reactor trip or initiation of any plant safety systems. Therefore, operation of the facility in accordance with the proposed change does not affect the probability or consequences of an accident previously evaluated.
(2) Create the possibility of a new or different kind of accident from any accident previously evaluated.
No change to normal operating procedures is involved and thus no new path is created which may lead to a new or different kind of accident.
The proposed change is intended solely to enhance the ability of the operator to diagnose accidents and transients by providing the operator with additional corroborative information.
Therefore, operation of the facility in accordance with the proposed change does not create the possibility of a new or different accident from any accident previously evaluated.
(3)
Involve a significant reduction in margin of safety.
The specific purpose of the proposed amendment is to enhance accident and transient monitoring capability and, thus, there is no significant decrease in the margin of safety.
Therefore, operation of the facility in accordance with the proposed changes does not involve a significant reduction in margin of safety.
V.
Implementation We request that the amendment approving this TSCR be made effective when the Reactor Coolant Inventory Trending System is declared operable.
VI.
Amendment Fee Pursuant to the provisions of 10 CFR 170.21, enclosed is a check for
$150.00 as payment of the fee associated with this TSCR.
VII.
References 1.
NUREG 0737, Item II.F.2 dated October 21, 1979 2.
NRC Order dated December 10, 1982 TABLE OF CCNTENTS Section Page 3,16 SHOCK SUPPRESSORS (SNUBBERS) 3-63 3.17 REACTOR BUILDING AIR TEMPERATURE 3-80 3.18 FIRE PROTECTION 3-86 3.18.1 Fire Detection Instrumentation 3-86 3.18.2 Fire Suppression Water System 3-88 3.18.3 Deluge / Sprinkler Systems 3-89 3.18.4 C02 System 3-90 3.18.5 Halon Systems 3-91 3.18.6 Fire Hose Statio'ns 3-92 3.18.7 Fire Barrier Penetration Seals 3-94 3.19 CONTAINMENT SYSTEMS 3-95 3.20 SPECIAL TEST EXCEPTIONS 3-95a 3.20.1 Low Power Natural Circulation Test 3-95a 3.21 RADI0 ACTIVE EFFLUENT INSTRUMENTATION 3-96 3.21.1 Radioactive Liquid Effluent Instrumentation 3-96 3.21.2 Radioactive Gaseous Process and Effluent Monitoring 3-100 Instrumentation 3.22 RADI0 ACTIVE EFFLUENTS 3-106 3.22.1 Liquid Effluents 3-106 3.22.2 Gaseous Effluents 3-111 3.22.3 Solid Radioactive Waste 3-118 3.22.4 Total Dose 3-119 3.23 RADIOLOGICAL ENVIRONMENTAL MONITORING 3-120 3.23.1 Monitoring Program 3-120 3.23.2 Land Use Census 3-125 3.23.3 Interlaboratory Comparison Program 3-127 3.24 REACTOR COOLANT INVENTORY TRENDING SYSTEM 3-128 l
4 SURVEILLANCE STANDARDS 4-1 4.1 OPERATIONAL SAFETY REVIEW 4 -1 4.2 REACTOR COOLANT SYsiDT TNSERVICE INSPECTION 4-11 4.3 TESTING FOLLOWINC OPENING OF SYSTEM 4-28 4.4 REACTOR BUILDING 4-29 4.4.1 Containment Leakage Tests 4-29 4.4.2 Structural Integrity 4-35 4.4.3 Deleted 4-37 4.5 EMERGENCY LOADING SEQUENCE AND POWER TRANSFER, EMERGENCY 4-39 CORE COOLING SYSTEM AND REACTOR BUILDING COOLING SYSTEM PERIODIC TESTING 4. 5.1 Emergency Loading Sequence 4-39 4.5.2 Emergency Core Cooling System 4-41 4.5.3 Reactor Building Cooling and Isolation System 4-43 4.5.4 Decay Heat Removal System Leakage 4-45 4.6 EMERGENCY POWER SYSTEM PERIODIC TESTS 4-46 l
111 l
Amendment No. 72, 81, 108 l
l
3.24 Reactor Coolant Inventory Trending System (RCITS)
Applicability Applies to the operability requirements for the Reactor Coolant Inventory Trending Systen (RCITS) ' an the reactor is critical.
Objectives To assure operability of RCITS instrumentation which may be useful in diagnosing situations which could represent or lead to inadequate core cooling.
Specification 3.24.1 Reactor Coolant Inventory Trending System (RCITS)
(a) One channel of the two channels shall be OPERABLE. A channel is composed of a hot leg level and a RV head level. With no channels OPERABLE, operation may continue and immediately initiate corrective action to return at least one channel to OPERABLE status as soon as possible.
If at least one channel is not restored within 30 days, details shall be provided in the Monthly Operating Report.
These details shall include cause, action being taken and projected date for return to OPERABLE status.
(b) One void fraction channel in each Reactor Coolant loop shall be OPERABLE. With no channels OPERABLE, operation may continue and immediately initiate corrective action to return at least one channel to OPERABLE status as soon as possible.
If at least one channel is not restored within 30 days, details shall be provided in the Monthly Operating Report.
These details shall include cause, action being taken and projected date for return to OPERABLE status.
Bases The RCS Inventory Trending System (RCITS) provides indication of the trend in water inventory in the hot legs and reactor vessel during the approach to inadequate core cooling (ICC).
In this manner RCITS provides additional information to the operator to diagnose the approach of ICC and to assess the adequacy of responses taken to restore core cooling.
3-128
The RCITS is required to be operable (as defined previously) when the plant is critical.
The RCITS is an information system to aid the operator during the approach to inadequate core cooling. There is no regulatory limit for this system.
Inoperability of the RCITS removes the availability of an information system.
Other useful instrumentation for inadequate core cooling will be available.
The RCITS is not a required system to mitigate evaluated accidents.
It may be useful to have the RCITS operable but will not cause an adverse impact if it is not operable.
The LC0 action statement provides the level of emphasis required for an information system.
This allows the plant to continue to operate and not to force an unneeded shutdown.
Refere nce FSAR 0; date Section 7.3.2.2.c.10 i
l i
l I
3-1 29
[
TABLE 4.1-1 (Continued) s g
CHANNEL DESCRIPTION CHECK TEST CALIBRATE REMARKS 4
- 49. Saturation Margin Monitor S(l)
M(1)
R (1) When Tave is greater than 525'F.
g (1) When T ve is greater than 250*F.
50.
Emergency Feedwater Flow NA M(1)
R m
a Instrumentation
- 51. Emergency Feedwater Initiation a.
Loss of RCPs NA Q(1)(2)
R (1) When Tave is greater than 250*F.
b.
Loss of Both Feedwater Pumps NA Q(1)(2)
R (2) Includes logic test only.
- 52. Backup Incore Thermocouple M(1)
NA R
(1) When Tave is greater than 250*F.
Display
- 53. RCS Inventory Trending System a.
Level NA NA R
o g
b.
Void Fraction W
NA R
S - Each Shift T/W - Twice per week R - Each Refueling Period D - Daily B/M - Every 2 months NA - Not Applicable W - Weekly 0 - Quarterly B/W - Every two weeks M - Monthly P - Prior to each startup if not done previous week