ML19199A429
| ML19199A429 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 10/12/1977 |
| From: | Rosa F Office of Nuclear Reactor Regulation |
| To: | Silver H, Wetmore J Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7905020132 | |
| Download: ML19199A429 (10) | |
Text
DISTRIBUTION:
d'M C0CKET FILE 007 13 $77
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NRR READING PSB READING FASHE READING ME"0RANDUM FOR:
H. Silver, Project Manager, Light Water Reactors 4, DPM J. Wetmore, Standard Technical Specification Group, DOR FROM:
Faust Rosa, Chief, Power Systems Branch, DSS
SUBJECT:
COMMENTS ON THE PROOF AND REVIEW COPY OF THE THREE MILE ISLAND UNIT NU4BEP. 2 TECHNICAL SPECIFICATIONS In act.oros..m with Joseph McGour menorandum dated August 24, 1977 conceming the above subject, tht attached enclosure provides the Pcwer Systems Branch cocmants on the Prcof and Review Copy of the Three Mile Island Unit Number 2 Technical Specifications.
These ceccents also reflect certain instrumentation and controls as well as selected electrical power systen design aspects of the Three Mile Island Unit Number 2 Nuclear Station.
The major conments reflect the inclusion of the periodic testing requirements of R.G.1.108.
Gy 50 k OcEj Fau & c 7 R W r
it Rosa, Chief Power Systems Branch Division of Systere Safety
Enclosure:
As stated cc:
S. Hanauer R. Mattson R. Tedesco R. Boyd W. Mcdonald S. Varga J. Glynn F. Rosa J. McGough F. Ashe 7 9 0 5 0 2 013E 4
Contact:
Frank Ash?
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ENCLOSURE COMMENTS ON THE PR00F AND REVIEW COPY OF THE THREE MILE ISLAND UNIT N0. 2 TECHNICAL SPECIFICATIONS Item 8, Table 2.2-1 (page 2-6) does nct contain the " trip setpoint" 1.
or " allowable values" for the watt transducers utilized by the reactor coolant pump electrical pcwer monitor circuitry. We recommend that these values be added to this table.
Item 3, Table 3.3-1 (page 3/4 3-11) does not contain an entry for 2,
It is manual initiation of the reactor building ') ray system.
recommended that such an entry (3c) be added to this item.
For item Sa, Table 3.3-3 (page 3/4 3-11) the electrical schematics 3.
for the Feedwater Latching System indicates that the entry in the
" channel to trip" column is not correct. Based on these electrical schematics we recommend that both the " channels to trip" and
" minimum channels operable" columns be changed to read (2 or selected 1 of 2)/ St.. Line.
4.
Items 7, Table 3.3-4 (pages 3/4 3-16 and 3/4 3-17) have no
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entries in tha columns for " trip setpoint" and " allowable values" concernin; the volts and time delays. These values are available and should be noted in this table.
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. 5.
Certain information provided in Table 3.3-5 (pages 3/4 3-18 and 3/4 3-19) is not consistent with the docketed information provided in Table 22.29-3 of the FSAR. Of primary concern in this regard are items 2h(2) and 6 of Table 3.3-5.
J.
We recommend that Section 4.8.1.1.2, item a (page 3/4 8-2) be modified as follows:
In accordance with the frequency specified in Table 4.8-1 a.
on a STAGGEREC TEST BASIS by:
1.
Verifying the fuel level in the day and engine-mounted fuel tank.
2.
Verifying the fuel level in the fuel storage tank.
3.
Verifying the fuel transfer pump can be started and transfers fuel from the storage system to the day and engine-mounted tank.
4.
Verifying the' diesel starts from ambient condition and accelerites to at least (900) rpm in 1 (10) seconds.
5.
Verifying the generator is synchronized, loaded to 3, (continuous rating) kw in 1 (60 seconds), and operates for 3, 60 minutes.
6.
Verifying the diesel generator is aligned to provide standby power to the associated emergency busses.
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TABLE 4.8-1 DIESEL GENERATOR TEST SCHEDULE Number of Failures In Last 100 Valid Tests
- Test Freauency
<1 At least once per 31 days 2
At least once per 14 days 3
At least once per 7 days
>4 At least orce per 3 days
" Criteria for determining number of failures and number of valid tests shall be in accordance with Regulatory Position C.2.e of Regulatory Guide 1.108, Revision 1, August 1977, where the last 100 tests are determined on a per nuclear unit basis.
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u W-STS 3/4 8-4b Section 4.8.1.1.2, item c (page 3/4 8-3) does not reflect the 7.
current staff position concerning degraded and/or low grid voltage or the recommendations contained in Regulatory Guide 1.108.
Accordingly, we recommend that the information contained in this item (c) of the technical specifications be replaced with the following draft cooy of infonnation (this draft copy of informia-tion is being incorporated into the Westinghouse Standard Technical Specifications);
At least once per 18 months during shutdown by:
c.
Subjecting the diesel to an inspection in accordance 1.
with procedures prepared in conjunction with its manu-facturer's recommendations for this class of standby service.
Verifying that the automatic load sequence timer is 2.
OPERABLE with the interval between each load block within
+ 10% of its design intervals.
Verifying the generator capability to reject a load of 3.
> (continuous rating) kw without exceeding 75% of the difference between nominal speed and the overspeed trip setpoint, or 15% above nominal, whichever is lower.
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4.
Verifying the generator capability to reject a load of
> (largest single emergency load) kw while maintaining voltage at i
volts and frequancy at i
Hz.
5.
Simulating a loss of offsite power by itself, and:
a) Verifying de-energization of the emergency busses and load shedding from the emergency busses.
b) Verifying the diesel starts from ambient condition on the auto-start signal, energizes the emergency busses with permanently connected loads, energizes the auto-connected shutdown loads through the load sequencer and operates for > 5 minutes while its generator is loaded wich the shutdown loads.
6.
Verifying that on an ESFAS test signal (without loss of offsite power) the diesel generator starts on the auto-start signal and operates on standby for > 5 minutes.
7.
Verifying tha't on a simulated loss of the diesel generator (with offtite power not available), the loads are shed from the emergency busses and that subsequent loading of the diesel generator is in accordance with design requirements.
lv c,.
. Simulating a loss of offsite power in conjunction with an 8.
ESFAS test signal, and Verifying de-energization of the emergency busses and a) load shedding frem the emergency busses.
Verifying the diesel starts from ambient condition on b) the auto-start signal, energi:es the emargency busses with pemanently connected loads, energizes the auto-connected emergency (accident) loads through the load 5 minutes while its sequencer and operates for 1 generator is loaded with the emergency loads.
Verifying that all diesel generator trips, except engine c) overspeed and generator differential, are automatically bypassed upon loss of voltage en the emergency bus actuation signal.
concurrent with a safety features Verifying the diesel generator operates for at least 24 9.
During this test the diesel generator shall be loaded to
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hours.
Within 5 minutes after completing 1 (continuous rating) kw.
this 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> test, repeat Specification 4.8.1.1.2.c.3.
Verifying that the auto-connected loads to each diesel 10.
generator do not exceed the continuous rating of Kw.
t i.
y,
9
- 11.
Verifying the diesel generator's capability to:
a) Synchronize with the offsite power source while the generator is loaded with its emergency loads upon a simulated restoration of offsite power, b) Transfer its load to the offsite power source, and c)
Proceed through its shutdown sequence.
- 12. Verifying that with the diesel generator operating in the test mode (connected to its bus), a simulated ESFAS signal will over-ride the test mode by (1) returning the diesel generator to standby operation and (2) autcmatically energizing the accident loads on offsite power.
8.
Also for Section 4.8.1.1.2 we recomend that an item d be added to this section as noted below:
d.
At least once per,10 years or after any modifications which could affect diesel generator interdependence by starting both diesel generators simultaneously, during shutdown, and verifying that both diesel generators accelerate to at least (900) rpm in <(10) seconds.
9.
Follcwing the addition of the abcve Section 4.8.1.1.2d we recomend that an additional section (4.8.1.1.3) be added to the technical specifications which states the following:
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, 4.8.1.l.3 Reoorts - All diesel generator failures, valid or non-valid, shall be reported to the Commission pursuant to Specification 6.9.1.
If the number of failures (on a per nuclear unit basis) in the last 100 valid tests is > 7, the report shall be supplemented to include the additional infomation recommended in Regulatory Position C.3.b of Regulatory Guide 1.108, :levision 1, August, 1977.
- 10. We recommend that the information contained on page 83/4 8-1 be modified as noted below:
3/4.8 ELECTRICAL POWER SYSTEMS BASES The OPERABILITY of the A.C. and D.C. power sources and associated distribution systems during operatior, ensures that sufficient power will be available to supply the safety related equipment required for 1) the safe shutdown of the facility and 2) the mitigation and control of accident conditions within the facility.
The mininum specified independent and redundant A.C. and D.C. power sources and distribution systems, satisfy the requirements of General Design Criteria 17 of Appendix "A" to 10 CFR 50.
The ACTION requirements specified for the levels of degradation of the power sources provide restriction upon continued facility operation commensurate with the level of degradation.
The OPERABILITY of the power sources are consistent with the initial condition assumptions of the accident analyses and are based upon maintaining e
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& at least one redundant set of onsite A.C. and D.C. power sources and associated distribution systems OPERABLE during accident con-ditions coincident with an assumed loss of offsite power and single failure of the other onsite A.C. source.
The OPERABILITY of the minimum specified A.C. and D.C. power sources and associated distribution systems during shutdown and refueling ensures that 1) the facility can be maintained in the shutdown or refueling condition for extended time periods and 2) sufficient instrumentation and control capability is available for monitoring and maintaining the facility status.
The Surveillance Requirements for demonstrating the OPERABILITY of the diesel generators are in accordance with the recommendations of Regulatory Guides 1.9 " Selection of Diesel Generator Set
' Capacity for Standby Power Supplies", March 10, 1971, and 1.108 " Periodic Testing of Diesel Generator Units Used as Onsite Electric Power Systens at Nuclear Power Plants", Revision 1, August 1977.
- 11. The last paragraph on page B3/4 3-1 states that the design of the Reactor Building Pump Suction, Feedwater Latching and Feedwater Line Rupture Detection do not meet all of the redundancy and independence requirements of engineered safety features instrument systems.
It is recommended that additional bases be provided in this paragrapn for this statement.
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