ML20069K657
| ML20069K657 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 04/22/1983 |
| From: | POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK |
| To: | |
| Shared Package | |
| ML20069K648 | List: |
| References | |
| NUDOCS 8304260433 | |
| Download: ML20069K657 (9) | |
Text
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ATTACHMENT I PROPOSED TECHNICAL SPECIFICATION CHANGES RELATED TO REACTOR PROTECTION SYSTEM ELECTRICAL PROTECTION ASSEMBLIES 9
l POWER AUTHORITY OF THE STATE OF NEW YORK JAMES A.
FITZPATRICK NUCLEAR POWER PLANT DOCKET NO. 50-333 I
o l
8304260433 830422 PDRADOCK05000gg l
P d
~
3.9 (cont ' d) 4.9 (cont'd) 3.
From and after the time both power supplies are made or found inoperable the reactor shall be brought to cold condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
G.
REACTOR PROTECTION SYSTEM ELECTRICAL G.
REACTOR PROTECTION SYSTEM ELECTRICAL PROTECTION ASSEMBLIES PROTECTION ASSEMBLIES Two RPS electrical protection assemb-lies for each inservice RPS MG set The RPS electrical protection assemblies and inservice alternate source instrumentation shall be determined shall be operable except as specified operable by:
below:
1.
At least once every 6 months, 1.
With one RPS electrical protection performing a channel functional assembly for an inservice RPS MG test.
set or an inservice alternate power supply inoperable, restore the 2.
At least once per operating cycle, inoperable channel to operable demonstrating the operability of status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or remove over-voltage, under-voltage and the associated RPS MG set or under-frequency protective' instrumentation alternate power supply from by performance of a channel calibration service.
including simulated automatic actuation of the protective relays, tripping 2.
With two RPS electrical protection logic and output circuit breakers and assemblies for an inservice-RPS verifying the following set points:
MG set or an inservice alternate power supply inoperable, restore at least one to operable status RPS MG SET _ SOURCE within 30 minutes or remove the associated RPS MG set or alternate OVER-VOLTAGE
$L132V power supply from service.
$s4s Time Delay UNDER-VOLTAGE 2108V
$L4s Time Delay UNDER-FREQUENCY 7tS7HZ
$14s Time Delay Amendment No. jE[
222c (continued on page 222d)
JAFNPP 3.9.G (cont'd) 4.9.G (cont'd) 3.
With the reactor in the RUN mode, at least one '(1) RPS division ALTERNATE SOURCE shall be powered from the MG OVER-VOLTAGE sl32V set except as specified below:
64s Time Delay With both RPS divisions powered UNDER-VOLTAGE
> 10 8V from the alternate sources, at
- 64s Time Delay least one division power source shall be restored to a MG set UNDER-FREQUENCY 2?57HZ with operable electrical 514s Time Delay protection assemblies within seven (7) days or the reactor.
shall be brought: to the cold condition within the subsequent 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Amendment No.
222d
JAFNPP 3.9 BASES (cont'd)
F.
Reactor Protection System Power Supplies Each of two RPS divisions may be supplied power from it's respective RPS MG set or from an alternate source which derives power from the same electrical division.
The MG sets and alternate sources for both divisions are provided with redundant,..
seismic qualified, class lE electrical protection assemblies between the power source and the RPS bus.
Any abnormal output type failure in either of the MG sets or alternate sources (if in service) would result in a trip of one or both of the electrical protection assemblies producing a half scram on that RPS division and retaining full' scram capability in the other RPS division.
Limiting operating conditions in Section 3.9.G provide a high degree of assurance that RPS buses are protected as described above.
Amendment No.
224a
9 JAFNPP
+
4.9 BASES (cont'd)
D.
Battery System Measurements and electrical tests are conducted at specified intervals to provide indication of cell condition and to determine the discharge capability of the batteries.
3 E.
LPCI MOV Independent Power Supply Measurement and electrical tests are-cond6cted at specified intervals to provide indication of cell condition, to determine the discharge capability of the battery.
F.
Reactor Protection Power Supplies Functional testes of the electrical protection assemblies are conducted once cadh six (6) months utilizing a built-in test device and once per operating cycle by performing an instrument calibration which verifies i
operation within the limits of Section 4.9.G.
e e
Amendment No. )MI 226
l ATTACHMENT II SAFETY EVALUATION l
RELATED TO REACTOR PROTECTION SYSTEM ELECTRICAL PROTECTION ASSEMBLIES I
i POWER AUTHORITY OF THE STATE OF NEW YORK JAMES A.
FITZPATRICK NUCLEAR POWER PLANT DOCKET NO. 50-333 l
k J
g Section I --Description of the Change This proposed amendment to Appendix A_of the James A. FitzPatrick' Nuclear Power Plant Facility Operating License includes two new.
Sections, 3.9.G and 4.9.G, on pages 222c and 222d.
These sections add operability and surveillance requirements for Reactor Protection System (RPS) Electrical Protection Assemblies., Corresponding Bases Sections have been added on pages 224a and 226 which describe-the purpose of each limiting condition or surveillance requirement.
The associated equipment is described in References (b), (e) and (m).
Section II - Purpose of Change Reference (i) describes deficiencies identified by the NRC in
.the design of the Hatch 2 regulator system for the motor generator
'(MG) sets which supply power to the reactor protection system
~
( RPS ).
The problem involved the possibility of the MG producing power of a quality outside the limits acceptable to the RPS.
The Authority responded to the Commission's concern via Reference (j).
The NRC reviewed the Authority response and determined that FitzPatrick plant could experience the same adverse conditions.
Modifications-to provide fully redundant Class 1E protection at the interface of the non-class 1E power supplies and RPS were prescribed.
The NRC further stated that the conceptual design proposed for modification of Hatch 1 was an acceptable solution.
In Reference (f), the Authority committed to upgrade the RPS based on General' Electric's Hatch 1 modification.
Conceptual design information for this modification was submitted to the NRC via Reference (b).
Model Technical Specifications were originally provided to the Authority in Reference (c) and later revised by Reference ~ (h ) ~.
Additional information and drawings requested by Reference (c) were supplied via References (e) and (m).
These proposed changes incorporate applicable portions of the sample Technical Specifications included with Reference (h).
Section 4.9.G requires the functional test of the electrical protection assemblies every six months and a demonstration of the i
operability of over-voltage, under-voltage and under-frequency protection once per operating cycle.
The Electrical Protection Assemblies (EPA) trip setpoints are I
within the limits described in Reference (1).
Reference (1) will be revised by General Electric Co. in the near future to reflect a four second allowable time delay.
These Technical Specification amendments, if approved, will fulfill the commitments referred to in References (b), (e) and (m).
Section III - Impact of the Change The proposed changes to the Technical Specifications impose new surveillance requirements.
The. changes improve the reliability of the RPS to more closely meet the criterion of IEEE Standard 379-1977, Reference (g).
In accordance with Reference (i), the Authority has been conducting a program of augmented surveillance since August 11, 1978' on the RPS power supply system.
The installation of this protective equipment and the attached technical specifications eliminate the need for this additional surveillance.
Therefore, this surveillance will be discontinued upon approval of these changes.
These changes to the FitzPatrick Technical Specifications, along with the RPS power supply modifications described in References (b),
(e) and (m) will eliminate the possibility of the MG set producing power of a quality outside the limits acceptable for the RPS.
The modifications provide redundant Class lE protection at the interface of the non-Class lE power supplies and RPS.
The Technical Specifications changes proposed will ensure the reliability and operability of this equipment.
Section IV - Implementation of the Change The change, as proposed, will not impact the ALARA or Fire Protection Program at FitzPatrick.
The proposed change will not' impact the environment.
Section V - Conclusion The incorporation of these changes:
a) will not change the probability nor the consequences of an accident or malfunction of equipment important tc safety as previously evaluated in the Safety.
I Analysis Report; b) will not increase the possibility of an accident or malfunction of a different type.than any evaluated previously in.
4 the Safety Analysis Report; c) will not reduce the margin of safety as defined in the basis for any Technical Specification; and d) does not constitute an unreviewed safety question.
Section VI - References (a) James A. FitzPatrick Nuclear Power Plant Final Safety Analysis, revised July 14, 1982.
(b) May 13, 1981 letter, J.P. Bayne (PASNY) to T.A. Ippolito (NRC) regarding Reactor Protection System Power Supply Upgrade (JPN-81-36).
(c) September 2, 1981 letter, T.A. Ippolito (NRC) to G.T. Berry l
(PASNY) regarding Reactor Protection System (RPS) Power Monitoring System Design Modification.
(d) September 24, 1980' letter, T.A.
Ippolito (NRC) to G.T. Barry (PASNY).
(e) November 2, 1981 letter, J.P. Bayne (PASKY) to T.A.
Ippolito
-(NRC) (JPN-81-87).
(f) January 19, 1981 letter, J.P. Bayne (PASNY) to T.A.
Ippolito (NRC) regarding RPS Power Supply (JPN-81-8).
(g) IEEE Standard 379-1977, "IEEE Standard Application of the Single-Failure Criterion to Nuclear Power Generating Station IE Systems."
(h) July 28, 1982 letter, D.B. Vassallo (NRC) to L.W.
Sinclair (PASNY) regarding RPS Power Monitoring System Design Modification.
(i) August 7, 1978 letter, T.A.'Ippolito (NRC) to G.T. Berry (PASNY).
(j). October 6, 1978 letter, P.J.
Early (PASNY) to T.A. Ippolito (NRC), (JNRC-78-49).
(k) Janes A. FitzPatrick Nuclear Power Plant, Special Engineering Test Report TP-1, Revision 1, "RPS Electrical Components Undervoltage Withstand Test" (1) General Electric Company, Installation Specification No. 22A7730 (m) February 23,-1982 telecon, J. Hegner (NRC) to L. Guaquil (PASNY), J. Escarzaga (PASNY), I. Ahmed (NRC) and J. Selan (LLNL) i 1
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