ML19206A528
| ML19206A528 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 06/01/1976 |
| From: | Arnold R Metropolitan Edison Co |
| To: | Kniel K Office of Nuclear Reactor Regulation |
| References | |
| GQL-0797, GQL-797, NUDOCS 7904200104 | |
| Download: ML19206A528 (12) | |
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IVETHOPOLI FAN EDISON COMPANY PCST CFFICE ECX 542 REACING. PENNSYLVANI A 19603 1 E LE PMGAeE-215 - 929-2601 s's Q s.W i
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.a I'ceket 70. SC-32C Attached is informaticn which vill 'ce incc porated inte Ana-4-a ' -1 tc the
""- -2 FSAR. 2is infonaticn serres to dccu ent cur responses to your requests for information whick=== "ecessar r in crder fer you cc issue the a.' a. '..t 3. ta' a'. d n C.. a_,c.-*. ( c:'.. ) '
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4-4-a auy r.e. a.. % 2 '. 4, 1976, ACES hearing.
Please ccte that the attached inic =ation v
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Sincerely,
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TAFLE 3.10-1 (Cont'd.)
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(Cont'd.)
(18) Contact Buffer Modules energize 40 ma g
de-energize 100 ms (19) Logic Buffer Module 10 ms (20) Unit Control Module Trip 50 ms g.
The applicant shall provide reactor coolant pump status Reactor coolant pumIi status monitors monitors and detectora which shall have a combined and detectora have a cenbir.ed accuracy accuracy of 0.88% and a renponse time of 6 ma or less, of 0.88% or better. The status monitor responce time required to protect the core during conntdmat of four pumps is, w
D as deceribed in Secticn 15.1.5 and
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Question CP.39, 2hD ns, a
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The applicant shall provide a description of and Reference ret.ponse to Question 22.29 g
procedures for testing to assure that the equipment in more accurate than and responds in a shorter time thrin the limits presented in requirements (d), (f),
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and (g) above.
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SRISOR TDIE CONSTANTS Plant Variable Requir ed Typical Sensor Sirn Int. ion ValueL Tested Value Pressure (Motorola)
Decrease Preauure 250 ms 25 mn Temperature
- Increase Temperature 177 GY 3.0 sec.
3.25 sec. 177 IlU 5.0 uec.
5.25 sec.
1 Reactor Coolant Flow Decrease Flov 240 ms 110 mu Reactor Coolant Pump Monitor"*
Loca of Pumps 210 ms 210 ms 4
g 7
1 CD Reactor Building Pressure""
Increase Pressure 260 ms Lecs than 100 mc*""
(Barton)
"The required value is based on a 60 ft/sec. flow, whereas the tested value is Laced on 3 ft/uec.
g flow which in conservative.
""Provides a digital (on--off) signal.
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"""Ik.nufacturers information.
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Plant Survev A general survey of the unit was conducted in order to determine any potential hacards resulting frca coderate energy line failures.
The survey resulted in identification of a Domestic Water (D.O.) service line (3/4") in the overhead of the Control Building Area, East Section, elevation 230' 6",
where failure could potentially jeopardice the Energency Feeduater Pump "otors.
To prevent failure of the E=ergency Feedwater Pump Motors the portion of the D.O.1.ine in questica will be isolated frca the balance of the systen by administratively naintaining D0-V-35 closed.
Thus, f ailure of this line will not affect the EE! =cters.
Except as noted above, there are no coderate energy line failures that can csuse a unit trip and result in the loss of both redundant trains of any safety related system.
Furthermore, no moderate energy line f ailure results in a loss of redundancy in any safety systes required to mitigate the effects of the failure.
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- Beltline region r.sterials available for surveillance pregras Notes (1) No r.aterial avail..hle (2) Estimted value S2-1771 1 - 4 cc Ga
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Question 2.1 ' 6, C.
The ECCS evaluation has not been completed by the staf f relative to TMI-2.
Provide a mass balance during the core flooding line break to verify the water level in the core.
Resconse The ECCS analysis of the core flooding line break is reported in Sectica 6.3.3.3 of the FSAR. The results of the analysis shcws that the liquid level in the core re=ains at or above 6.25 f t af ter 200s.
This is sufficient to keep the core covered by a two-phase =ixture and =aintain the cladding terperature
~
vithin a few degrees of saturation.
Figure 1 presents the leak flow rata, the core boil-off rate and the injection rate for the anlaysis af ter 200s. As can be seen, the cc=bined injection rate (1 CFT and 1 EPI) is greater than the core boil-off rate.
Therefore, the liquid level in the core will be =aintained. After 900 seconds, tEc EPI injection rate exceeds the core boil-off rate and long-ter= cooling is assured.
While the leak rate is not exceeded by the injection rate until 600s, only steam is being relieved through the break.
The relief of steaa through
- -l m a h des the break will centinue to depressurize the syste= until, the core boil-off rate 6qt.ala theisteaming. Since the inj ection sys ten exceeds the boil-off f
^
rate, the analysis need not be continued past 900s as the capability to provide long-ters cooling has been demonstrated.
It is important to note that a conservative bubble rise assumption was used in the analysis presented in the FSAR.
The liquid level in the core is conservatively low as the Redfield bubble rise correlatien was used in CRAFT. As demonstrated in Section 6.3.3.3 of the FSAR, use of the more realistic bubble rise correlation, (twice times the Wilson correlation) results in 1.75 ft more liquid in the core.
Use of twice the bubble rise 4 em
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/
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velocity calculated by the 'Jilsen correlation results in a more consistent mixture height calculation between C?lFI and FCf.'i.
As de=onstrated, the core liquid level reported in the FSAR is maintained due to the ceabined injection of one CFT and one PSI pump.
After 900s, the one HFI pu=p provides sufficient injection to makeup for core boil-off and will provide long ter= cooling capability.
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