ML19339A183
| ML19339A183 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 10/20/1980 |
| From: | Varga S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19339A184 | List: |
| References | |
| NUDOCS 8011030209 | |
| Download: ML19339A183 (10) | |
Text
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(m) g(f***o%jo UNITED STATES g
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NUCLEAR REGULATORY COMMISSION
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DUQUESNE LIGHT COMPANY OHIO EDISON COMPANY PENNSYLVANIA POWER COMPANY DOCKET NO. 50-334 BEAVER VALLEY POWER STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 34 License No. DPR-66 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Duquesne Light Company, Ohio Edison Company, and Pennsylvania Power Company (the licensees) dated October 17, 1980, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's nJ1es and regulations set forth in 10 CFR Chapter I;
B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (id) that such activities will be conducted in compliance with the Comission's regulations; D.
The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
1 8 0110 3 0fo9-
2-2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-66 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised throcgh Amendment No. 34, a re hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION r'ga,d Operating Reactors Branch #1 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: October 20, 1980 e
S e
ATTACHMENT TO LICENSE AMENDMENT AMENDMENT N0. 34 TO FACILITY OPERATING LICENSE NO. DPR-66 DOCKET NO. 50-334 Revise Appendix A as follows:
Remove Pages Insert Pages 3/4 7-26 3/4 7-26 3/4 7-27 3/4 7-27 3/4 7-32 3/4 7-32 3/4 7-32b 3/4 7-32b 3/4 7-32d 3/4 7-32d e
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PLANT SYSTEMS 3/4.7.11 RESIDUAL HEAT REMOVAL SYSTEM - T,yg < 350*F LIMITING CONDITION FOR OPERATION 3.7.11.1 As a minimum, one residual heat removal subsystem shall be OPERABLE.
APPLICABILITY: MODES 4 and 5.
ACTION: With no Residual Heat Removal subsystem OPERABLE, imediately restiffe at least one RHR subsystem to OPERA 8LE status or maintain the Reactor Coolant System T less than 350*F by use of alternate heat removal methods.
avg SURVEILLANCE REQUIREMENTS 4.7.11.1 The Residual Heat Removal subsystem shall be demonstrated OPERABLE per the applicable Surveillance Requirements of Specification 4.7.10.1.
BEAVER VALLEY - UNIT 1 3/4 7-25
PLANT SYSTEMS 3/4.7.12 HYDRAULIC SNUBBERS LIMITING CONDITION FOR OPERATION 3.7.
12 All hydraulic snubbers listed in Table 3.7-4 shall be OPERABLE.
I APPLICABILITY: MODES 1, 2, 3 and 4.
ACTION:
With one or more hydraulic snubbers inoperable, restore the inoperable snubber (s)~ to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE REQUIREMENTS 4.7.
12.1 Each hydraulic snubber with seal ma'terial fabricated from l
ethylene propylene or other materials demonstrated compatible with the operating environment and approved as such by the NRC, shall be deter-mined OPERABLE at least once after not less than 4 months but within 6 months of initial criticality and in accordance with the inspection schedule of Table 4.7-4 thereafter, by a visual inspection of the snubber.
Visual inspections of the snubbers shall include, but are not necessarily limited to, inspection of the hydraulic fluid reservoirs, fluid connec-tions, and linkage connections to the piping and anchors.
Initiation of the Table 4.7-4 inspection schedule shall be made assuming the unit was previously at the 6 month inspection interval.
4.7.
12.2 Each hydraulic snubber with seal material not fabricated from ethylene propylene or other materials demonstrated compatible with the operating environment shall be detemined OPERABLE at least once per 31 days by a visual inspection of the snubber. Visual inspections of the snubbers shall include, but are not necessarily limited to, inspection of the hydraulic fluid reservoirs, fluid connections, and linkage connections to the piping and anchors.
BEAVER VALLEY - UNIT 1 3/4 7-26 Amendment No. E, 34
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' PLANT SYSTEMS _
HYDRAULIC SNUBBERS (Continued)_
SURVEILLANCE REQUIREMENTS (Continued) l During shutdown,18 months after initial criticality and at 4.7.
12.3 least once per 18 months thereafter, a representative sample of at least 10 snubbers or at least 10% of all snubbers listed in Table 3.7-4, which-ever is less, shall be selected and functionally tested to verify correct Snubbers selected for functional pisten movement, lock up and bleed.
testing shall be selected on a rotating basis except snubbers identified in Table 3.7-4 as either "Especially Difficult to Remove" or in "High Radiation Zones" may be exempted from functional testing provided these snubbers were demonstrated OPERABLE during previous functional tests.
Snubbers found inoperable during functional testing shall be restored to OPERABLE status prior to resuming operation. For each snubber found inoperable during these functional tests, an additional minimum of 10" of all snubbers or 10 snubbers, whichever is less, shall also be functionally tested until no more failures are found or all snubbers have been functionally tested.
I i
l BEAVER VALLEY - UNIT 1 3/4 7-27 Amendment No. 2, 34 i
TABLE 3.7-4 SAFETY RELATED HYDRAULIC SNUBBERS
ON, LOCATION AND ELEVATION INACCESSIBLE 70NE TO REMOVE
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RC-IIC-1A RC RCP Cub. A 736'6" I
Yes Yes RC-IlC-2A RC RCP Cub. A 731'2" RC-IIC-3A 736'6" g
RC-HC-4A 736'6" q
RC-HC-SA 728'2" RC-HC-6A 736*6" RC-ilC-7A 728'2" RC-HC-8A 731'2" RC-HC-9A 766'10" RC-IIC-10A 766'10" RC-IIC-11A 766'10" RC-IIC-12A 766'10" RC-HC-1B RC RCP Cub. B 728'2" RC-lic-28 728'2" R
RC-IIC-3B 731'2" RC-HC-4B 736'6" y
RC-IIC-SB 736'6" g
RC-HC-68 736'6" RC-IIC-78 736'6" RC-IIC-8B 731'2" sI f
a
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TABLE 3.7-4 (Continued)
SAFETY RELATED llYDRAULIC SNUBBERS *
.'d SNiilillfit SYSTEM SNUBBER INSTALLED ACCESSIBLE OR lilGil RADIATION ESPECI ALLY DIrflCill.T
_.-...O_._.
ON, LOCATION AND ELEVATI0N INACCESSIBLE ZONE TO REMOVE N -.
.I
- E-RC-llSS-101 RC.RCP Cub. A 739' I
Yes Yes
'a RC-IISS-102 739' SI-ilSS-102A SI 745' c
SI-1155-1020 "
745' a
.5 51 -l155-414 741'
~'
RC-IISS-103 RC RCP Cub. B 739' RC-IISS-104 739'
~~~
S1-1155-418 SI 741' RC-IISS-23 RC Reac. Cnt. Bldg.
749' A
No No 1:C -IISS-105 RC RCP Cub. C 739' I
Yes
.Yes RC-IISS-106 RC 739' SI-IISS-114A SI 745' 745' S 1-1155-114B "
SI J65-422 741' SI-l.35-423 739' Y
RC-usS-22 RC Pressurizer Cub.
784' A
Yes Yes d
RC-liSS-41 A 734' A
ItC-IISS-44 A 784' A
RS-IISS-235 RS Reac. Cnt. Bldg.
832' I
No l'.S-IISS 210 817' RS-IISS-211 817' T
- S-1155-213 800' i
ItS-IISS-214 000' il its-IISS-222 814' RS-IISS-223 014' Y,
RS-IISS-224 813' 013' li RS-IISS-225 WFPD-IISS-201FW 780' A
No No N
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TABLE 3.7-4 (Continued)
SAFETY RELATED HYDRAULIC SNUBBERS
'jj NO.
ON, LOCATION AND ELF'dATION INACCESSIBLE ZONE TO RENVE h
RC-HSS-119 RC Reac. Cnt. Bldg.
734' A
Yes No p,
SI-HSS-409 SI 729' No SI-HSS-410 7 31 '
SI.HSS-411 7 31 '
E kS-HSS-201 RS 731' Yes a
7 31 '
q RS-HSS-202 RS-HSS-237 7 31 '
No m
RS-IISS-238 731' RS-HSS-229 731' RS-HSS-236 7 31' RS-HSS-234 726' I
CC-ilSS-405A "
707' I
Yes Yes w
707' 3
CC-IISS-405B "
711' CC-IISS-407A "
y a.
CC-IISS-407B "
711 '
RS-IISS-205 RS 702' A
No No RS-HSS-206 702' RS-HSS-219 702' RS-HSS-220 702' 702' RS-HSS-207 RS-HSS-208 702' RS-HSS-209 710' RS-HSS-215 715' RS-HSS-216 715' E
Ril-HSS-10S RH 704' I
Yes Yes RH-HSS-107 704'
[
RH-HSS-108 704' s
Ril-HSS-Ill 704' n
i TABLE 3.7-4 (Continued)
SAFETY RELATED HYDRAULIC SNUBBERS
ON, LOCATION AND ELEVATION INACCESSIBLE ZONE TO REMOVE
?
E WR-HSS-3048 RW Cable Vault 728' A
No No 733' g
WR-HSS-316 a
a 733' E
WR-HSS-306
=
=
a 731' G
WR-HSS-308 a
=
7 31 '
WR-ilSS-309 a
a WR-HSS-300 724' a
731 '
SI-HSS-522 SI a
SI-HSS-523A "
731'
=
731' SI-HSS-5238 "
a a
731' SI-ilSS-521 a
a SI-ilSS-516A "
731' a
SI-HSS-516B "
731*
a w
7 31 '
D SI-ilSS-520 a
7 31' SI-HSS-515 a
u 731' k
SI-HSS-Sib a
a 731' ca.
S1-1155-514
=
7 38' SI-HSS-512 SI-ilSS-512A "
734' 51-1155-511 738' a
51-1155-518 733' S1-115S-517 738' a
2r QS-IISS-504 QS Safeguards Area 741' R
n QS-ilSS-205A QS 735' a
z QS-ItSS-205B "
735' QS-HSS-202 737' p
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