ML18092A375
| ML18092A375 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 10/15/1984 |
| From: | Public Service Enterprise Group |
| To: | |
| Shared Package | |
| ML18092A374 | List: |
| References | |
| LCR-84-14, NUDOCS 8411210010 | |
| Download: ML18092A375 (4) | |
Text
PROPOSED CHANGE TECHNICAL SPECIFICATIONS SALEM GENERATING STATION UNIT NO. 1 DESCRIPTION OF CHANGE Ref:
LCR 84-14 Technical Specifications Heatup and Cooldown Curves, Figures 3.4.2 and 3.4.3 shall be replaced with the attached revised figures.
REASON FOR CHANGE This change is required to comply with Tech. Spec. Surveillance Requirement 4.4.9.1.2.
10CFR 50.92 SIGNIFICANT HAZARDS EVALUATION Eight surveillance capsules for monitoring the effects of neutron exposure on the Salem Unit No. 1 reactor vessel core region material were inserted, prior to initial plant startup, in the reactor vessel between the thermal shield and the vessel wall, vertically centered on the core mid plane.
Capsule Twas removed after approximately two years (l.08 effective full power years) of plant operation.
Post-irradiation mechanical testing of the Charpy V-notch and tensile specimens was performed at the Westinghouse Research and Development Remote Laboratory in accordance with 10CFR50, Appendices G and H.
Capsule T contained passive neutron flux monitors for the purpose of neutron dosimetry.
Westinghouse testing showed agreement between the measured neutron fluence level of 2.56 x 1018 neutrons/cm2 and the calculated fluence level of 2.89 x 1018 neutrons/cm2 for Capsule T.
Since the calculated fluence level was based on core power distributions derived for long term operation, and while the Capsule T data are representative of only Cycle 1 operation~ projection of vessel toughness into the future is based on analytically based fluence curves.
Heatup and cooldown limit curves are calculated using the most limiting value of RT-NDT (reference nil-ductility temperature).
The most limiting RT-NDT of the material in the core region is determined using the preservice reactor vessel material properties and estimating the neutron radiation induced RT-NDT shift.
8411210~10. 841015 PDR ADOCK 05000272 p
PROPOSED CHANGE TECHNICAL SPECIFICATIONS.
SALEM GENERATING STATION UNIT NO. 1 Ref:
LCR 84-14 The figures attach~d to this LCR are the revised heatup and cooldown curves developed from the Capsule T analysis performed by Westinghouse.
Derivation of these curves was based on Appendix G, ASME III, 1977 and Summer 1978 Addenda. The analysis results were transmitted in* WCAP 9678 *.
The results of the surveillance capsule anal~sis indicate that the reactor.vessel has adequate toughness for.continued saf~
operation.
Adherence.to the revised heatup and *cooldown curves.
would ensure. the prevention of nonductile f~ilui~.
This change
- will be in accordance with. the requirements of Tech. Spec.*
Surve(llance Requirement 4.4.9.1.2 for Unit No. land would not*
involve any Significant Hazatds Consideratio~.
Since the new curves wiil result in more conservative operation of the reactor vessel, there is no increase. in the probability or consequences of any accidents nor are any new accidents.
introduced.
Margins of safety are incieased -by the. more
- donservative operation~
Since this change introduces curves which are a more stringent limit on operation, it conforms to example (ii) of*
. " *** ~men.dments That Are Not Likely To. Involve* Significant
.Hazards Considerations" as provided by the.Commission in Federal Register 48FR14870;
3000
- 2000 t:>
en
~ -
w a:
=>
en en w
c:
~
0 w t-<
(.)
0 z 1000 0
MATERIAL PROPERTY BASIS
-- CONTROLLING MATERIAL: INTERMEDIATE SHELL
-- COPPER CONTENT:
0.24 WT%
I
-- PHOSPHORUS CONTENT:
0.010 WT%
I LEAK TEST --- RT NOT INITIAL:
45°F
~LIMJ.T
-- RT NOT AFTER 10 EFPY:
1/4T, 183° F 3/4T, 134°F
'"'" 1-CURVE APPLICABLE FOR HEATUP RATES r
r
'"'" "" UP TO 60°F/HR FOR THE SERVICE PERIOD '
'"'"... UP TO 10 EFPY AND CONTAINS MARGINS I r
_._ OF 10° F AND 60 PSIG FOR POSSIBLE INSTRUMENT ERRORS.
~
~,,
J
/,,
4
.4 CRITICALITY LIMIT BASED ON INSERVICE HYDROSTATIC TEST 1-'
TEMPERATURE HEATUP RATES II (329°F) FOR THE UP TO 60°F/HR-P#PJ y SERVICE PERIOD UP TO 10 EFPY.
~,
~-....
0 100 200 300 400 INDICATED TEMPERATURE (° F)
Figure l.4=~ Salem Unit No. l Reactor Coolant System Heatup Limitations Applic~b1e for the First 10 EFPY.
500 SAUM UNIT 1 3/4 4-26
3000 2000 C)
Q..
w cc
=> "' "'
w cc Q..
0 w
(.)
c z 1000 0
MATERIAL PROPERTY BASIS
""""'CONTROLLING MATERIAL: INTERMEDIATE SHELL COPPER CONTENT:
0.24 WT%
....... PHOSPHORUS CONTENT:
0.010 WT%
...... RT NOT INITIAL:
4S°F
....... RT NOT AF.TEA 10 EFPY:
1/4T, 183° F J
3/4T, 134° F I
CURVE APPLICABLE FOR COOLDOWN RATES
....... UP TO 100°F/HR FOR THE SERVICE PERIOD j
........ UP TO 10 EFPY AND CONTAINS MARGINS OF,
...... 10°F AND 60 PSIG FOR POSSIBLE INSTRUMENT ERRORS'.
I
~
J j
I I
J COOL DOWN
~I
""' RATES °F/HR
"""'.I.
~~I.)
0
., ?
I~ :::...
20---
1~ _...
~
40---
- so--
- ioo--
I 0
100 200 300 400 INDICATED TEMPERATURE (°F)
Figure 3.4-3 Salem Unit No. 1 Reactor Coolant System Coc1dovm Limitations.Applicable for the First 10 EFPY SALFM UNIT 1 3/4 4-27