ML19253B525
| ML19253B525 | |
| Person / Time | |
|---|---|
| Site: | Haddam Neck, Millstone File:Connecticut Yankee Atomic Power Co icon.png |
| Issue date: | 10/09/1979 |
| From: | Counsil W NORTHEAST UTILITIES |
| To: | Ziemann D Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7910160359 | |
| Download: ML19253B525 (22) | |
Text
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RTFOR CONNECTICUT 06101
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October 9,1979 Docket Nos. 50-213 50-245 50-336 Director of Nuclear Reactor Regulation Attn:
Mr. D. L. Ziemann, Chief Operating Reactors Branch #2 Mr. R. Reid, Chief Operating Reactors Branch #4 U.
S. Nuclear Regulatory Commission Washington, D. C.
20555
References:
(1)
W. G. Counsil letter to D. L. Ziemann and R. W. Reid dated April 11, 1979.
(2)
W. G. Counsil letter to D. L. Ziemann and R. W. Reid dated May 18, 1979.
(3)
W. G. Counsil letter to D. L. Ziemann 7nd R. W. P.eid dated July 31, 1979.
(4)
D.
Ziemann letter to W. G. Counsil dated October 3,1978.
(5)
'). L. Ziemann letter to W. G. Counsil dated September 26, 1978.
(6)
.t.
W. Reid letter to W. G. Counsil dated September 19, 1978.
Gentlemen:
Haddam Neck Plant Millstone Nuclear Power Station, Unit Nos. 1 and 2 Additional Information, Fire Protect' n In References (1), (2), and (3), Connecticut Yankee A t ;mic Power Company (CYAPCO) and Northeast Nuclear Energy Company (NNECO) respon #1 to the open items enumerated in the original fire protection safety evaluations which were issued by References (4), (5), and (6) for each of the three operating units.
Verbal communications with the NRC Staf f on docketed information have identified a need for further clarification. Attachments (1), (2), and (3) provide this clarification and formally resolve these items.
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. It is our current understanding that the attached material, which supplements References (1), (2), and (3), is sutficient to fully resolve the Section 3
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concerns of References (4 ), (5), and (6).
Implementation of hardware modifica-tions is now in progress to fulfill the license conditions of DPR-61, DPR-21, and DPR-65.
Very truly yours, CONNECTICUT YANKEE ATOMIC POWER COMPANY NORTHEAST NUCLEAR ENERGY COMFANY 1
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't7 Mt 9 W.' 'G. 'Counsil Vice President Attachment j
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Docket No. 50-213 ATTACHMENT 1 HADDAM NECK PLANT FIRE PROTECTION ADDITIONAL INFORMATION OCTOBER, 1979
NRC-SER ITEM 3.1.5 AUXILI ARY BUIIDING SPRINKLER SYSTEM NRC Concern Area sprinklers will be provided in the area of cable trays with two divisions of safety related cables in the auxiliary building.
Response
The sprinkler system concent for the auxiliary building as defined in the April 11, 1979, W. 'G. Coensil to D. L.
Ziemann package has been changed.
The new c6ncept, as discussed and resolved with NRC, is as shown in attached sketch.
Please note that this design is intended to provide general area protection as well as cable tray protection.
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PRIMARY _
AUXIUARY BUILDING BulLDIMG SPRINKLE R SYSTEM
_El. 34'-t " _
AUXILIARY BLD&. CEIUN&
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and C44/c Troy Pdden Heds 8' on Center
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P THIS SPRINKLER CONCEPT IS INTENDED TO PROVIDE CABLE TRAY PROTECTION AS WELL AS GENERAL AREA PROTECTION.
THIS SKETCH IS INTENDED TO REFLECT THE CONCEPT INVOLVED AND ACTUAL DESIGN WILL BE DEVELOPED BY OUR CONTRACTED VENDOR.
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NRC-SER ITEM 3.1.11 PORTABLE VENTILATION EQUIPMENT NRC Concern Portable ventilation equipment will be provided at strategic locations throughout the plant for fire brigade use.
Response
Per telephone conversation with NRC on August 21, 1979, the concern was the type of equipment being provided.
Connecticut Yankee has purchased portable ventilation equipment which included three (3) 16" Model P-164, 5200 CFM, 115 V, Super Vac Smoke Ejectors.
Refer to attached information.
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17395 5*'d '*' Conn. Yankee Atomic Power Co.
Injun Hollow Rd.
Haddam Neck, Conn.
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Aug. 9, 1979 c......r. o.a., N.. 487613 y,. ;
CERTIFICATE OF CONFORMANCE This certificate of conformance is to certify that the material supplied on purchase order 487613 is in accordance with the spec-ifications and requirements set forth and they meet and or exceed U.L. or N.F. code standards.
Shipman's Fire Equipment Co.Inc.
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NRC-SER ITEM 3.1.18 REACTOR COOLANT PUMP OIL COLLECTION SYSTEM NRC Concern An oil collection system will be provided for each of the reactor coolant pumps or a fire retardant synthetic oil will be used.
Response
The oil' collection system for the RCP's at Connecticut Yankee was defined in Attachment I of W. G. Counsil to D. L. Ziemann letter of April 11, 1979.
The only change to the design parameters pro-vided in April is that reference to the 55 gallon drums for oil collection / storage should be deleted.
The oil collection / storage system will be of sufficient capacity to collect the entire inventory of one complete RCP lube oil failure.
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NRC-SER ITEM 3.2.3 CABLE FIRE BARRIER PENETRATIONS TEST DATA NRC Concern Test data will be provided to demonstrate the adequacy of electrical cable fire barrier penetration.
Response
Electrical cable fire barrier penetration test data was provided in a previous submittal (W.
G. Counsil to D.
L, Ziemann, July 31, 197s).
In addition to this, supplemental test data has been provided by our barrier penetration installer (ICMS) and is attached.
All seals referenced as three hour fire rated, in attached IC?!S letter, have been installed in accordance with ASTM E-119.
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September 18, 1979 Northeast Utilities Service Comp;ny P;0. Box 270 Hartfori. Connecticut 06101 Attention:
Electrical Engineer
Subject:
Silicone foam seals installed at Connecticut Yankee Power Plant Dear Mr.
All the silicone foam penetration seals installed at the referenced plant have been installed as three (3) hour fire seals.
The only exceptions are as follows:
Reference the Penetration Survey for Zone S-8 Switchgear, Elevation 41'6" floor, Drawins, No. 24098, Sheet No. 71.
Nos. 840, 841, 842, 844, 846, 847, 850, 851, 853, 855 and 856.
The above mentioned penetrations are electrical blockouts 16" x 12" with four 4" conduits penetrating :he blockout.
The conduits have been filled with 1" of damming and 6-1/2" of silicone foam. The remaining area of the blockout has also been filled with 1" of damming and 6-1/2" silicone foam.
According to our test data on blockouts we must put in 9" of silicone foam to achieve a three (3) hour rating.
We feel we must point cut that the floor is only 6" thick and that tl e foam is extending 1-1/2" above the floor at this time.
All other silicone foam seals have sufficient test data to achieve a three (3) hour rating.
)q, INSULATION CCNSULTANTS & MANAGEMENT SERVICES,INC.
POST OFFICE BOX ONE / BARODA. MICHIGAN 49101/ 616 422-2112
A September 18, 1979 Page Two Y
The penetrations listed above as exceptions are scheduled for retrofit in October of 1979 to comply as three (3) hour fire seals.
Respectfully, m
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Docket No. 50-245 ATTACHMENT 2 MILLSTONE NUCLEAR POWER STATION, UNIT NO. 1 FIRE PROTECTION ADDITIONAL INFORMATION
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OCTOBER, 1979
NRC-SER ITEM 3.1.4 MOTOR GENERATOR SET CUF9ED AREA SPRINKLER SYSTEM NRC Concern An automaite sprinkler system will be installed to provide coverage over the cui5ed area of the motor generator set.
Response
The sprinkler system to be installed is as documented in Attachment 2 of W.
G.
Counsil to D.
L. Ziemann letter of April 11, 1979.
The only clarification required is that this sprinkler system will provide coverage for the entire curbed area rather than a water curtain type system.
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Docket No. 50-336 ATTACHAENT 3 MILLSTONE NUCLEAR POWER STATION, UNIT NO. 2 FIRE PROTECTION ADDITIONAL INFORMATION
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NRC-SER ITEM 3.1.14 REDUNDANT CABLES IN CONTAINMEN7 NRC Concern Where redundant cables in conduit are exposed to cable tray fire hazards in the containment, they will be protected by suitable fire barriers or the cables in conduit will be rerouted.
Response
During the NRC Site Fire Protection Inspection, redundant conduit (Z R033, Z R032, Z R043) were identified as being located directly 1
3 4
above a 29 cable tray (Z 24AF20).
The concern was that e cable tray 9
fire could involve redundant facility.
An evaluation of this con-cern revealed that the Z2 cable tray fire loading was negible (two nonvital cables).
It was concluded that since neither the redundancy nor the fire hazard existed, no additional protection was required.
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NRC-SER ITEP! 3. 2.1 CABLE SPREADING AREA NRC Concern The licensee will conduct an evaluation to determine a suitable method to provide isolation, separation, or protection of redundant safety related cables in the cable spreading area.
Response
The noted evaluation was conducted and documented in W. G. Counsil to D.
L.
Ziemann letter of July 31, 1979.
NRC conducted an inspection of this fire zone on August 31, 1979 to evaluate the acceptability of NNECO's proposed modifications.
It was agreed that modifications proposed by NNECO in the referenced letter were acceptable.
The only clarification required is that the sprinkler systera proposed would be a specially designed system to direct water between trays rather than general area protection.
An understanding was also reached that the recommended fire retardant barriers, to separate redundant facilities within this sprinklered area, would be deleted to allow proper water coverage.
Water tie-in point would be such that isolating the referenced sprinkler system would not affect the existing cable spreading area manually operated deluge system.
In addition to NNECO's recommendations for the cable spreading area the NRC has requested that the additional modifications should be implemented.
1.
Combustible penetration damming material should be removed.
2.
Fire rated damper should be installed in the two ventilation f cilities.
openings of the block wall separating Z1 and Z2 NNECO/NUSCO have reviewed these additional recommendations and agree to implement.
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NRC-SER ITEM 3.2.2 PROTECTION OF REDUNDANT CABLE TRAYS NRC Concern The consequences of fire damage to systems required for safe shutdown will be determined where the physical separation of cables in the auxiliary building may not preclude damage to redundant safety related systems.
Fire retardant coating, automatic sprinkler, suitable fire barriers or early warning detection will be provided to assure that fire damage does not result in a loss of shutdown capability where prompt action is not taken to suppress fires in these areas.
Response
The requested evaluation for the auxiliary building was completed and recommendations for corrective action were documented in Attach-ment 3 of W.
G. Counsil to D.
L. Ziemann letter of July 31, 1979.
NRC's inspection of August 31, 1979 resulted in the following changos:
1.
Elevation -45',
Zone 1A, Column F.8/H.2 and 16.6/17.2 NNECO's original recommendation as documented in the July 31, 1979 response, was to place ionization detectors above the cross over and install fire rated barriers to separate the two tray facilities in question.
A eview of these recommendations and discussions with the NRC resulted in the following changes:
The cross over involving redundant divisions will be pro-tected by a fixed sprinkler system which will be fed from the existing water stand pipe system.
Proposed fire rated barriers and special detection will be deleted.
2.
Elevation -45',
Zone A-1A, Columns F.8/H.2 and 17.2/18.4 No change, as documented in the July 31, 1979 package.
3.
Elevation -25',
Zone A-9, Charging Pump Area No change, as documented in the July 31, 1979 package.
4.
Elevation
-5',
Zone A-18, Column F.3/F.8 and 18.9/19.6 Pipe Penetration Roou In addition to recommendations proposed
.n the July 31, 1979 package, tray covers will be provided for cable tray sections involved in the cross overs.
Tray covers will extend beyond the the immediate cross over area to prevent heat concentration at cross over area in case of fire, i'
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NRC-SER ITEM 3.2.2 PROTECTION OF REDUNDANT CABLE TRAYS 5.
Elevation
-5',
Zone A-14 Columns F.8/H.2 and 18.1 In addition to recommendations proposed in the July 31, 1979 package, the clothing storage rack will be relocated to re-duce combustible exposure to S/R cable trays.
6.
Elevation 5',
Zone A-14, Columns L.5/M.4 and 17.7 No change, as documented in the July 31, 1979 package.
7.
Elevation 5',
Zone A-14, Columns M.4 and 17.8 No change, as documented in the July 31, 1979 package.
8.
Elevation 14'6",
Zone A-27D, Columns M.7 and 18.9/20.0 NNECO's original recommendation as documented in the July 31, 1979 response, was to provide detectors at the tray cross over area and provide fire rated barriers to separate the redundant facilities.
A review of this area and dis-cussions with the NRC, resulted in the following modifications for this area.
The cross over involved will be protected by an automatic sprinkler system fed from the adjacent railroad access area sprinkler system.
This system will also extend about 15' into fire zone A-27D to provide additional protection to S/R cables.
Originally proposed detection and fire rated barriers will be deleted.
9.
Elevation 14'6",
Zone A-24, Columns H.2/H.4 and 17.1/17.5 No change, as documented in the July 31, 1979 package.
10.
Elevation 14'6",
Zone A-24, Columns F.8/H.2 and 17.4 In addition to recommendations proposed in the July 31, 1979 package, Sections of Z2 trays will be provided with tray covers.
Tray cover will extend beyond the immediate cross over area to prevent heat concentration at cross over area in case of fire.
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NRC-SER ITEM 3.2.4 CABLE FIRE BARRIER PENETRATION TEST DATA NRC Concern Test data will be provided to demonstrate the adequacy of electrical cable fire barrier penetrations.
Response
Electrical cable fire barrier penetration test data was provided in a previous submittal (W.
G. Counsil to D. L.
Zi emann, July 31, 1979).
In addition to this, supplement test data has been provided by our barrier penetration installer (ICMS) and is attached.
All seals referenced as three hour fire rated, in attached ICMS letter, have been installed in accordance with ASThf E-119.
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September 18, 1979 Northeast Utilities Service Company P.O. Box 270 Hartford, Connecticut 06101 Attention:
Electrical Engineer
Subject:
Silicone foam seals installed at Millstone 2 Power Plant Dear Mr.
All the silicone foam penetration seals installed at the referenced plant have been installed as three (3) hour fire seals.
The only exceptions are as follows:
1.
Reference the Penetrat, ion Survey for Zone T-16 Cable Vault, Elevation 25'6".
Nos. 408, 409, 601, 613, 615, 616, 617, 618, 619, 636, 800, 801, 802, 803, 804, 805, 1000, 1001, 1002, 1003 and 1016.
2.
Reference the Penetration Survey for Zone T-21 Control Room, Elevation 36'6".
Nos. 883, 911, 967, 968, 955A, 967A, 969A, 835B, 854B, 856B, 862B, 863B, 864B, 865B, 871B, 873B, 874B, 895B, 900B, 915B, 916B, 922B, 926B, 927B, 928B, 929B, 936B, 940B, 953B and 954B.
The above mentioned penetrations have been sealed with a minimum of 6" silicone foam plus 1" damming, which, in most cases, is the thickness of the penetrated structure.
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INSULATION CONSULTANTS & MANAGEMENT SERVICES,INC.
POST OFFICE BOX ONE / BARODA. MICHIG AN 49101/ 616 422-2112
A September 18, 1979 Page Two T
All of these penetrations can be repaired to achieve the necessary fire rating, with all necessary documentation, by the end of 1979.
NOTE: Test documentation will be available in six weeks from this date.
R g ectfully,,,,
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